digital.library.unt.edu/67531/metadc1055659/m2/1/high_r… · DISCLAIMER This report was prepared...

TREE-NUREG-1136 for U.S. Nuclear Regulatory Commission

LOFT SYSTEM STRUCTURAL RESPONSE DURING SUBCOOLED BLOWDOWN

JOHN S. MARTINELL

January 1978

n ~~ EC311C3 Idaho, Inc.

!)S ,_I

q5o / IDAHO NATIONAL ENGINEERING LABORATORY

DEPARTMENT OF ENERGY 0

IDAHO OPERATIONS OFFICE UNDER CONTRACT EY-76-C-07-1570

DISTRIBUTION OE I.HtS O.OC.U.MEti"t IS UtiUMIIEO

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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Pr ice : Printed Copy $~; Micro fiche $3.00 7. ;J..S'""

"The NRC will make available data tapes and operational computer codes on research programs deal ing with postulated loss-of-coolant accidents in light water reactors . Persons requesting this information must reimburse the NRC contractors for their expenses in preparing copies of the data tapes and the operational computer codes. Requests should be submitted to the Research Applications Branch , Office of Nuclear Regulatory Research, Nuclear Regulatory Commission , Washington , D.C. 20555."

NOTICE-------------,

This report was prepared as an account of work sponsored by the United States Government. Neither the the United States nor the Department of Energy, nor the Nuclear Regulatory Commission , nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information , apparatus, product o r process disclosed, or represents that its use would not infringe privately owned rights.

LOFT SYSTEM STRUCTURAL RESPONSE

DURING SUBCOOLED SLOWDOWN

Approved:

L. P. Leach, Manager LOFT Experimental Program Division

N. C LOFT

,------NOTICE-------.

This report was prepared as an account of work sponsored by the United States Covemment. Neither the United States nor the United States Deputment of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or impUed, or assumes any ltgaJ llabUJi>: or responstbll.tty lOr the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned ri~Us.

DISTRIBUTION OE Il\IS Dl)CLIMENT 15 UNUMIT~

TREE-NUREG-1136

0

Distributed Under Category: NRC-2

Water Reactor Safety Research Systems Engineering

LOFT SYSTEM STRUCTURAL RESPONSE

DURING SUBCOOLED SLOWDOWN

By

John S. Martine11

EG&G Idaho, Inc.

January 1978

PREPARED FOR THE U.S. NUCLEAR REGULATORY COMMISSION

AND DEPARTMENT OF ENERGY

IDAHO OPERATIONS OFFICE UNDER CONTRACT NO. EY-76-C-07-1570

.ACKNOWLEDGMENTS

Appreciation is expressed to R. C. Guenzler, I. K. Hall, Jr.,

R. G. Rahl, V. T. Berta, L. D. Goodrich, and the personnel of the Loss

Of-Fluid Test .Oata Systems Branch·for their special help in. preparing

this document.

i i

ABSTRACT

The Loss-of-Fluid Test (LOFT) facility is a highly instrumented,

pressurized water reactor test system designed to be representative of

large pressurized water reactors (LPWRs) for the simulation of loss-of

coolant accidents (LOCAs). Detailed structural analysis and appropriate

instrumentation (accelerometers and strain gages) on the LOFT system

provided information for evaluation of the structural response of the

LOFT facility for loss-of-coolant experiment (LOCE) induced loads. In

general, the respbnse of the system during subcooled blowdown was small

with typical structural acceleratjons below 2.0 G's and dynamic strains

less than 150 x 10-6 m/m. The accelerations measured at the steam

generator and simulated steam generator flange exceeded LOCE design

values; however, integration of the accelerometer data at these

locations yielded displacements which were less than one half of the

design values associated with a safe shutdown earthquake (SSE), which

assures structural integrity for LOCE loads. ....

Use of the LOFT structural response data for reactor safety and

code qualification is not recommended due to the complexity. of the LOFT

system and to the problems associated with low amplitude data analysis.

The existing measurement system was adequate for evaluation of the LOFT

system response during the. LOCEs. The conditions affecting blowdown

loads during nuclear LOCEs will be nearly the same as those experienced

during the nonnuclear LOCEs, and the characteristics of the structural

response data in both types of experiments are expected· to be the same.

The LOFT system is concluded to be adequately designed and further

analysis of the LOFT system with structural codes is not required for

future LOCE experiments.

·I

iii

SUMMARY

The following subjects are addressed concerning the structural

response of the LOFT system during subcooled blowdown.

(1) The LOFT system ·structural response . relative to (a) the

experiment predictions and (b) the LOFT system design.

(2) The quality of the LOFT structural response data and applica

tions for reactor safety, code qualification, and LOFT

requal ification.

(3) The existing measurement system and recommendations for

repositioning and/or addition of new measurements.

(4) Projected changes in structural response data in nuclear LOCEs

relative to nonnuclear LOCEs.

(5) The need for additional analysis of the structural respon~~

data and/or LOFT system with structural codes.

The LOFT facility has been deiigned to r~prP.~sent: t,hP m~jnr

component and system thermal hydraulic responses of a LPWR during. a

LOCA. The test assembly includes five major subsystems which have been

extenstvely instrumented. so that ,desirable system parameters can be

measured and recorded during a LOCE. These subsystems were instrumented

for structural response. .measurements for purposes of assurance of the

adequacy of the LOFT structural design and requalification only. No

attempt was made to instrument for purposes of structunil t.:ullt:!

verification. The major subsystems include: (a) the reactor vessel,

(b) the primary coolant (intact) loop (c) the blowdown (broken) loop,

(d) the blowdown suppression system, and (e) the emergency core coolant

system.

iv

\

The Ll test series (nonnucl~ar blowdown tests) provided information

concerning equipment and system performance, structural adequacy, test

procedures, operator experience, and data for experimental verification

of thermal-hydraulic system behavior prior to nuclear blowdowns. In

particular, Experiments Ll-2, Ll-3, and Ll-3A were used.in this analysis

for addressing the subjects identified earlier. Structural response

data (accelerometer and strain gage data) in the intact and broken loops

and reactor vessel were reviewed and analyzed for comparison with

predicted and design values to evaluate the system response in these

areas. In general, the response of the system to LOCE loads· was small

rwith typical structural accelerations below 2.0 G and dynamic strains

less than 150 x 10-6 m/m. The measured accelerations from Experi

ment Ll-3A at the steam generator (AE-PC17-1 and AE-PC17-2) and the

simulated steam ~enerator flange (AE-BL2-l) exceeded the LOCE design

values. Quantification of the accelerometer data is highly subjective

since accuracy is poor due to the noise level in the measurements. A

more detailed analysis of the data at these locations (integration of

the acceleration plots) indicated that maximum deflections during sub

cooled blowdown were less than one half those associated with a safe

shutdown earthquake, assuring structural integrity for LOCE loads since

the system was designed for combined seismic and LOCA induced loads.

Due to the low magnitude of the LOFT structural response data, -quantification for direct comparison with predicted values is of

questionable value (strains only slightly larger than accuracy limits

and high noise level). Use of the data for reactor safety and code

qualification is not recommended due to the system complexity and the

problems involved in data reduction and evaluation. The LOFT data are

applicable for requalification purposes at LOFT but should not be relied

up~n solely, due to the problems associated with providing applicable

measurements at all points in the system (tees, welds, junctions, etc).

The requalification program will include a comprehensive inspection of

welds and components on intervals recommended by fatigue analysis. The

existing measurement system is deemed adequate for the purposes of

evaluating LOFT system structural response, and no recommendations for

repositioning or adding new measurements are ·made here. The data

v

associated with nuclear LOCEs should have the same characteristics as

the nonnuclear LOCE data since those conditions ~ffecting blowdown loads

are nearly the same in either case. Further analysis of the LOFT system

with structural codes for LOCE loads is deemed unnecessary.

The horizontal accelerations measured at the top of steam generator

(AE-PC17-l and -2) for ·nonnuclear LOCEs are two to three times the

values predicted by finite element analysis. This difference can, in

part, be explained by two techniques used in modeling the structure in

the area of the steam generator. First, the snubber supports as modeled

are loaded with any 1ncremental detlection, wh1le, 1n th~ phys1cal case,

a finite amount of displacement at the top o~ the steam generator 1s

required before the snubbers provide any restraint. Thus, low-amplitude

vibration can occur at· the top of the steam generator before lateral

restraint. occurs, for which the ·existing model can not account.

However, as the -amplitude of vibration increases, the modeled restraint

is a better representation of the physical restraint giving rise to

closer agreement between predicted and actual responses. Secondly, the

predicted accelerations are for the center of gravity of the steam

generator rather than at the top where the measurements were taken. Any

rotational motion about a horizontal axis would give rise to higher

acceleration at the top of the st~am g~nerator than pred1cted.

The acceleration measured in the east-west direction at the simu

lated steam generator flange (AE-BL2-l) exceeds the predicted LOCE value

by 17%. This difference is felt to .pe within· the allowable range of

accuracy associated with quantifying and comparing the measured data

with that predicted using finite element analysis.

Underprediction of the LOC~ accelerations at the steam generator

could give rise to questions concerning the predicted response for com

bined LOCA and seismic activity f.~r which the LOFT system is de~i_gned.

Review of the combined LOGA and seismic analysis of the mobile test

assembly reveals that response to those loads is two to three times as

severe as that measured during the nonnuclea~ L0C~s. Inspection of pre

d.icted load data for combined LOCA and seismic activity indi.cates the

vi

elastic factor of safety of the steam generator support beams is greater

than six. It is felt that this large factor of safety allows the

existing structure sufficient margin to accomodate any additional load

which may not have been predicted with the existing model.

. ... , ' .

vii

CONTENTS

ACKNOWLEDGMENTS

ABSTRACT

SUMMARY .

I. INTRODUCTION

II. SYSTEM CONFIGURATION

III. MEASUREMENTS AND INSTRUMENTATION

IV. EXPERIMENT CONDITIONS ..... .

V. DATA PRESENTATION AND DISCUSSION

VI. REFERENCES . . . . . . . . . . .

FIGURES

1. LOFT major components

2. Acceleration at simulated steam generator flange, East-West (AE-BL2-l) .............. .

3. Acceleration at simulated steam generator flange, North-South (AE-BL2-2) . . . . . . . . . . . .

4. Acceleration at simulated steam qenerator top, vertical (AE-BL3-l) ........ .

5. Acceleration at QOBV, cold leg, North-South (AE-BL4-1) . . .

6. Acceleration at QOBV, hot ieg, North-South (A[ DLS 1) . . . .

......

7. Acceleration at 90-degree-elbow downstream of primary coolant pumps, East-West (AE-PC3-l)

8. Acceleration at 90-degree-elbow downstream of primary coolant pumps, North-South (AE-PC3-2)

9. Acceleration at 90-degree-elbow downstream of primary coolant pumps, vertical (AE-PC3-3)

10. Acceleration at 45-degree-elbow in intact loop hot leg, East-West (AE-PCG-1) .

viii

i i

iii

iv

1

2

6

13

15

106

5

21

21

22

22

23

23

·24

24

25

11. Acceleration at 45~degree-elbow in intact loop hot leg, North-South (AE-PC6-2) .

12. Acceleration at 45-degree-elbow in intact loop hot ·leg, vertical (AE-PC6-3) . .

13. Acceleration at 90-degree-elbow in intact loop hot leg, East-West (AE-PC7-1) . .

14. Acceleration at 90-degree-elbow in intact loop'hot leg, North-South (AE-PC7-2)

15. Acceleration at primary coolant pump inlet, East-West (AE-PC16-l)

16. Acceleration at primary coolant pump inlet, North-South (AE-PC16-2) . . .

17. Acceleration at primary coolant pump inlet, vertical (AE-PC16-3) . .

18. Acceleration at steam generator north side, East-West (AE-PC17-l) . . .

19. Acceleration at steam generator north side, North-South (AE-PC17-2) . .

20. Acceleration at primary coolant pump 1 north side, East-West (AE-PC18-1)

21. Acceleration at primary coolant pump 1 north .side, North-South (AE-PC18-2) .

22. Acceleration at primary coolant pump 1 north side, vertical (AE-PC18-3) .

23. Acceleration at primary coohnt pump 2 north side, East-West (AE-PC19-l)

24. Acceleration at primary coolant pump 2 north side, North-South (AE-PC19-2)

25. Acceleration at primary coolant pump 2 north side, vertical (AE-PC19-3) .

26. Acceleration at bottom of reactor vessel, west side, East-West (AE-RVl-1)

27. Acceleration at bottom of reactor vessel,· west side, East-West (AE-RVl-2)

28. Acceleration at bottom of reactor vessel, west side, vertical (AE-RVl-3) . . . .

ix

.

.

. .

. .

. .

. .

25

26

26

27

27

28

28

29

. . . . . 29

30

. 30

31

31

. . 32

. . . 32

. 33

. . . 33

. . . 34

29. Acceleration at bottom of reacto~ vessel, north side, North-South (AE-RVl-4) . . . 34

30. Acceleration at bottom of reactor vessel, north side, North-South (AE-RVl-5) . . . . 35

31. Acceleration at bottom of reactor vessel, north side, vertical (AE-RVl-6) . 35

32. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l) 36

33. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-2) . . 36

34. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-3) . . . 37

35. Strain at reactor vessel broken loop cold leg no:a.l e (SE-BL8-4) . . . 37

36. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-5) . . . . 38


38. Strain at reactor vessel broken loop colJ leg nozzle (SE-BL8-8)· . . 39

39. Strain at reactor vessel broken loop cold· lP!J nn771P. (SE-AL8-9) . . . 39

40. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-ll) . 40

41. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-12) 40

42. Strain at reactor vessel broken loop hot ,~

leg nozzle (SE-BL9-l) . 41

43. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2) : 41

44. Strain at reactor vessel,broken loop hot leg nozzle (SE-BL9-4) . .• 42

45. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4) . 42

46. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) . ''• 43

x.

47. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6) . . 43

48. Strain between.pump and steam generator simulator (SE-BL27-2) . . . 44

49. Strain between pump and steam generator simulator (SE-BL27-4) . . . . . . . . . . 44

50. Strain between pump and. steam generator simulator (SE-BL27-5) . . . 45

51. Strain between pum~ and steam generator simulator (SE-BL27-6) . . . . . . . . . 45

52. Strain between pump and steam generator simulator (SE-BL27-8) . . . . 46

53. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l) . 46

54. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2) . . 47

55. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-4) . ... 47

56. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-5) . 48

57. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-7) . . . 48

58. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-8) . . . 49

59. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l) . . 49

60. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-2). . . . 50

61. Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-3) . . 50

62. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-4) . . 51

63. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-5) . . . . 51

64. Strain at reactor vessel intact loop hot. leg nozzle (SE-PC5-6) . . . 52

xi

65. Strain at reactpr vessel i~tact loop hot leg nozzle (SE-PC5-7) .

66. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-8) , . . .

67. Strain at reactor vessel intact loop hot leg nozzle (S.E-PC5-9)

68. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10) .

69. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll) .

70. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-12) ..

71. Strain at steam generator inlet ~ozzle (SE~PC14-2) . , . . . . . . ..

72. Strain at steam gener~tor inlet nozzle (SE-PC14-3)

73. Strain at ste~m generator inlet nozzle (SE.;.PC14-4)

74. Strain at steam generator inlet nozzle (SE-PC14-5)


76. Strain at steam generator inlet noz~le (SE-PC14-7)



79. Strain at steam generator inlet nozzle (SE-PC14-l0)

80. Strain at steam generator inlet nozzle (SE~PC14-12)

81. Strain at steam generator outlet nozzle (SE~PC15~1.).

82. Strain at steam generator outlet nozzle (SE-PClS-2)


84. Strain at steam generator outlet nozzle (SE-PC15-4)


86. Strain at steam generator outlet nozzle (SE-PC15~6)

xi i

52

53

53

54

54

5.5

55

56.

56

57

57

58

58

59

59

60

60

61

61

62

62

63


88. Strain at steam generator outlet nozzle (SE-PC15-9).


90. Strain at steam generator outlet nozzle (SE-PC15-ll)


92. Strain at primary coolant pump outlet (SE-PC18-13)


94. Str-ain at primary coolant pump outlet (SE-PC18-15)







101. Strain. at primary coolant pump outlet (SE-PC18-23)


i03. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l) . . . . . . . . .

104. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-2) • . .. . • • . . • • . • . .

105. Strain at reactor vessel broke~ loop cold leg nozzle (SE-BL8-3) . . . . . . . . . .

.106. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-4) . . .

107. Strain at reactor vessel broken loop cold leg nozzle (SE-81.8-5) . . . • . . • . . .

108. Strain at reactor· vessel broken loop cold leg nozzle (SE-BL8-6) . . . ; . . . . . ..

109. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-8) . . . . , , , . , . , , . . . . .

xiii

63

64

64

65

65

66

66

67

67

68

68

69

69

70

70

71

71

72

72

73

73

74

74

110, Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-9)

' . . . . . . . . . . . 75

111. Strain at reactor vessel broken 1oop cold leg nozzle (SE-BL8-ll) . . . . . 75


113. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l) . . . . . . . . . . . 76

114. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2) . . . . . . . 77

115. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-3) . . . . . 77

116. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4) . . . . . 78

117. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) .• . . . ' . . 78

118. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6) .

' . . . . . 79

119. Strain between pump and steam generator simulator (SF~Rl27-?.) . . . . . . . ' . . . . 79

120. Strain between pump and steam generator simulator (SE-BL27-4) . . . . . . 80

1£1. Strain between pump and steam generator simulator (SE-BL27-5) . . . . 80

122. Strain between ..

pump and steam generator simulator (SE-BL27-6) . . . . . 81

123. Strain between pump and steam generator simulat·or .. (SE-BL27-8) . . . 81

124. Strain at reactor vessei intact 1oop cold leg nozzle (:>t-PC4- 'I) . . 82

125. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2) . 82

126. Strain at reactor vessel intact ·loop co-ld leg nozzle (SE-PC4-4) . . . 83

127. Strain at reactor Vessel i'ntact loop cold leg nozzle (SE-PC4-5) . . . . . .83

xiv

128. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-7) . . . . . . . 84

129. Strain at reactor vess~l intact loop cold leg nozzle (SE-PC4-8)' . . . . . . 84

130. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-1) . 85

131. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-2) . . . . 85

132. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-3) .

" . 86

133. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-4) . . . . . . 86

134. Strain at reactor vessel intact loop hot leg· nozzle (SE-PC5-5) . . . . . 87

135. Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-8) . 87

136. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-9) . . . . . 88

137. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10) . . . . . 88

138. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll) . . . . 89

'

139. Strain at reactor vessel intact 1 oo"p hot leg nozzle (SE-PC5-12) . . 89

140. Strain at steam generator inlet nozzle (SE-PC14-2) 90







·147. Strain at steam generator inlet nozzle ($E-PC14-9) 93

XV



150. Strain at steam generator outlet nozzle (SE-PC15-l) 95

151. Strain at steam generator outlet nozzle (SE-PC15-2) 95

152·. Strain at steam generator outlet nozzle (SE~PC15-3) 96


154. Strain at steam generator outlet nozzle .. (SE-PC15-5) 97


156. Strain at steam generator· outlet nozzle (SE-PC15-8) . 98


158~ Strain at· steam generator outlet nozzle (SE-PC15.:.10) .. . 99

.159. Strain at steam generator ou·tle.t nozzle (SE-PC15:..1l} 99


161 . Strain at primary coolant pump out·l et· (SE-PC'JS-13) '100

162. Strain at primary coolant pump outlet (SE-P~18-14) 101

163. Strain at primary coolant pump outlet (SE-PC18-15) .1'01

164. Strain at primary coolant pump outlet (SE-PC18-16) 102


1.66. Strain at primary coolant pump outlet (SE-PC18-l8) 103

167. Strain at primary coo·l ant· pump outlet (SE-PC18-19) l03

168. Strain at primary coo.l ant pump outlet. (SE-PC18-21) 104

169. Strain at primary ·coo 1 ant pump outlet (SE,..PC18-22) 104

170. Strain at primary coolant pump out·l et (SE-PC18-23) 105


xvi

TABLES

I. Accelerometer Locations.

II. Strain Gage Locations ..

III. LOFT Ll-Series Experiment Conditions

IV. ·Summary of Accelerometer Data for Experiment Ll-3A

xvii

7

9

14

18

I. INTRODUCTION

The presentation of the loss-of-fluid test (LOFT) system structural

response during subcooled blowdown is addressed by the following:

(1) The response of the LOFT system relative to (a) experiment

predictions and (b) system design.

(2) The quality and magnitude of LOFT accelerometer and strain

gage data (structural response data).

(3) The applicability of LOFT structural response data for reactor

safety and/or structural

requalification.

code qualification and LOFT

(4) The quality, quantity, and position of existing and/or

proposed measurem~nts.

(5) The differences in structural response data from nonnuclear to

nuclear LOCEs.

(6) The need for further analysis of the existing structural

response data and/or the LOFT system with structural' codes.

This analysis concerns only the primary coolant system and blowdown

loop to the quick-opening blowdown valves (QOBVs) of the LOFT facility

as described in Section II of this

acquired with · the instruments

report.

described

. . Structural response

in Section III for and Ll-3A[ 1•2•3 •4 •5]

data

the

were nonnuclear series Experiments Ll-2, Ll-3,

reviewed. A brief descri~tion of the experiment

in Section IV. A complete set of accelerometer

conditions is included

and strain gage data

from the Ll-3A experiment is presented in Section V with an evaluation

and discussion.

. 1

II. SYSTEM CONFIGURATION

The LOFT facility has been designed to simulate the major

components and system thermal hydraulic responses of a large pressurized

water reactor (LPWR) during a loss-of-coolant accident (LOCA). The test

assembly is comprised of five major subsystems which have been

instrumented such that desirable system parameters can be measured and

recorded during a loss-of-coolant.experiment (LOCE). These subsystems

were instrumented for structural response me~surements for purposes of

assurance of the adequacy of the LOFT structural design and for

requalification only. No attempt was made to instrument fqr purposes of

structural code verification. The subsystems include: (a) the reactor

vessel, (b) the primary coolant (intact) loop, (c) the blowdown {broken) loop, (d) the blowdown suppression syst~m. and (e) ~he ~mergency core

cooling system (ECCS).

The LOFT reactor vessel simulates the reactor vessel of a LPWR. It

has an annular downcomer, a lower plenum, lower core suppbrt plates, a

core simulator, and an upper plenum. The downcomer connects with the

co 1 d ·1 eg_ of both the intact and broken 1 oops and contains two experi

mental instrument stalks; the upper plenum connects the hot leg of both

the intact and the broken loops. fhe core simulator conta1ns an exper1·

mental instrument stalk and hydraulic orifice plate assembly to simulate

the flow resistance of a nuclear core which will be installed for non

nuclear LOCE Ll-5.

The 1ntact luu!J ~ JmuldL~~ Lit~ uttut·ulo...t!tt loops of a LPWR. This loop

contains a steam generator, two circulating coolant pumps connected in

parallel, il prc~::;uriz.er, a venturi flowmeter, and connecting pipino.

For Experiment Ll-3A, the primary side steam generator inlet and outlet

plenums contained square-edged orifice plates sized for low resistance

or core flow area scaling. Thus these orifices provided a similar

pressure drop at scaled flow rates around the LOFT intact loop

(excluding the reactor vessel) as exists in a LPWR operating loop. The

secondary side of the steam generator was filled to a predetermined

2

level and isolated from the remainder of the secondary coolant system.

The intact loop circulating coolant pumps were used to bring the system

to the initial test temperature of 282°C.

The· broken loop simulates the broken loop of a LPWR. It consists

basically of hot and cold legs that are connected to the reactor vessel

and the blowdown suppression tank header. Each leg consists of a break

plane orifice which determines the break size to be simulated, a quick

opening blowdown valve (QOBV) which simulates a pipe break, a recircula

tion line, an isolation valve, a~d connecting piping. The recirculation

lines establish a small flow from the broken loop to the intact loop ·to

maintain these loop temperatures approximately equal prior to the blow

down. These recirculation paths are secured just prior to blowdown

initiation.

Experiments Ll-2, Ll-3, and Ll-3A simulated a 200% double-ended

shear break in a cold leg of a LPWR operating loop. In this configura

tion, the broken loop hot leg contained, in addition to the above

mentioned components, steam generator and pump simulators. These

simulators have hydraulic orifice plate assemblies installed which have

similar (passive) resistances to flow as a real pump and steam

generator. The break flow area (break plane orifice area) in this con

figuration is 0.0084 m2; this is 100% of the possible break flow area in

each line.

The blowdown suppression system simulates the containment back

pressure of a LPWR. This system is comprised of the blowdown

suppression· tank header, the blowdown suppression tank (BDST), the

nitrogen pressurization sy~tem, and the blowdown suppression tank spray

system (BDSTSS). The blowdown header is connected to the suppression

tank by four suppression tank downcomers that extend inside the tank and

discharge below the water level established as a test initial condition.

The nitrogen pressurization system is supplied by the LOFT inert gas

system and utlizies a remote controlled pressure regulator to establish

and maintain the specified BDST initial pressure. The spray system

consists of a centrifugal pump which discharges through a heatup heat

3

exchanger and either three spray headers or a pump recirculation line

that contains a cooldown heat exchanger. The spray pump suction can be

aligned to either the BDST or the borated water storage tank (BWST).

The three spray headers have 0.0013-, 0.0038-, and 0.0139 m3/s flow rate

capacities and are located in the BDST along the upper centerline; To

model the containment back pr~ssure of a LPWR, predetermined initial

conditions are established in the BDST.

The LOFT ECCS simulates the ECCS of a LPWR. The accumulator, the

high-pressure injection system (HPIS), and the low-pressure injection

system (LPIS) were used dur·ing the Ll-3A expet··iment. Each system was

configured to inject scaled volumetric flow rates of ECC directly into

the lower plenum of the re.;lctor vessel. To provide these scaled tlow

rates, accumulator ACC-A, HPIS pump A, and LPIS pump A were utilized.

Accumulator ACC-A was preset to inject ECC at a system pressure of

4.22 MPa. HPIS pump A was preset to inject at 0.001 m3/s and to

initiate by LOCE control at 22 s after the initiation of blowdown; LPIS

p~mp A was adjusted to in~tiate by LOCE control at 35.5 s after the

initiation of blowdown.

A detailed description of the LOFT facility can be found in

Reference 6. Only the first three subsystems mentioned above are

dis~ussed and a pictorial view is included in Figure 1.

4

Pressurizer

Steam Generator Outlet OTT Flange

Intact Locp Hot Le~; OTT

Vessel

Fig. l

Broken Loop Hot Leg OTT

Flange ·

ECC Lower Plenum lnje_ction Inlet

Intact Loop Cold Leg OTT Flange

LOFT major cq~ponents.

ANC-C-7002

Suppression Tank

III. MEASUREMENTS AND INSTRUMENTATION

The LOFT instrumentation system was designed to measure and record

the important parameters that occur during a LOCE. The .accelerometer

and str~in gage data from the locations summarized in Tables I and II

are. considered sufficient for use in the analysis presented herein.

Information on the calibration factors, accuracy, and response of

specific instruments is given in Reference 7. Reference 6 should be

consulted tor details of instrument design and locations.

Device Number

AE-BL2-l

AE-BL2-2

AE-BL3-l

AE-BL4-l

AE-BL5-l

AE-PC3-l

AE-PC3-2

AE-PC3-3

AE-PCG-1

AE-PCG-2

AE-PCG-3

AE-PC7-l

AE-PC7-2

AE-PC7-3

TABLE I

ACCELEROMETER LOCATIONS

Direction

East-West

North-South

Vertical

North-South

North-South

East-West

North-South

Vertical

East-West

North-South

Vertical

East-West

North-South

Vertical

7

Location

SimUlated steam generator flange

Simulated steam generator flange

Simulated steam generator top

Quick-opening blowdown valve, cold leg

Quick-opening blowdown valve, hot leg

90-degree-elbow downstream of primary coolant pumps

90-degree-elbow downstream of primary coolant pumps

90-degree-elbow downstream of priamry coolant pumps

45-degree-elbow between reactor vessel and steam generator



90-degree-elbow betwe~n reactor vessel and steam generator

90-degree-elbow between reactor vessel arid steam generator

90-degree-elbow between reactor vessel steam generator

TABLE 1 (continued)

Device Number Direction Location

AE-PC16-l East-West Primary coolant pump jnlet

AE-PCl6-2 .North-South Primary coolant pump inlet

AE-PC16-3 Vertical Primary coolant pump inlet

AE-PCl7-l East-We.st Steam generator, north side

AE-PC17-2 North-South Steam generator, north side

At-PCl 8- l cast-West Pr1ma.ry co·olanL IJUIIIIJ 1 , north side

AE-PC18-2 North-.South Primary coolant pump 1 , .north s.i de

AE-PC18-3 Vertical .Pri ma:ry ooo'lant pump 1 , nor·th s·ide

AE-PC19-l East-West Pri.mary coolant pump 2, north .side

AE-PC19"'".2 ·North-South Primary coo·l ant pump 2, no·rth si.de

AE-PCl9-3 VeY't i ca 1 Primary coolant pump 2, north side

AE-RVl-1 East-West Reactor vessei bottom., west side

AE--RV1 -2 Ea~t-West Reactor vessel ·bottom, west side

AE-- RVl· 3 Ve.rtic.Jl . ~a actor VQ»iel b?ttom, we~.t. side

AE- RVl-4 North-South Reactor vessel bottom, north side

AE-RVl-5 North-South Reactor vessel bottom, north side

AE-RVl-6 Vert i'cal 'Reactor vessel bottom, north side

TABLE II

STRAIN GAGE LOCATIONS

Device Number Position Location

SE-BL8-l Top-longitudinal Broken loop, cold leg nozzle

SE-BL8-2 Top-45 degrees Broken loop, cold leg nozzle

SE-BL8-3 Top-circumferential Broken loop, cold leg nozzle

SE-BL8-4 Right-longitudinal Broken loop, cold leg nozzle

SE-BL8-5 Right-45 degrees Broken loop, cold leg nozzle

SE-BL8-6 Right-circumferential Broken loop, cold leg nozzle SE-BL8-7[a] Bottom-longitudinal Broken loop, cold leg nozzle

SE-BL8-8 Bottom-45 degrees Broken loop, cold leg nozzle

SE-BL8-9 Bottom-circumferential Broken loop, cold leg nozzle SE-BL8-10[a] Left-longitudinal Broken loop, cold leg nozzle

SE-BLS-11 Left-45 degrees Broken loop, cold leg nozzle

SE-BLB-12 Left-circumferential Broken loop, cold leg nozzle SE-BL9-l Top-longitudinal Broken loop, hot leg nozzle

SE-BL9-2 Right-longitudinal Broken loop, hot leg nozzle

SE-BL9-3 Right-45 degrees Broken loop, hot leg nozzle

SE-BL9-4 Right-circumferential Broken loop, hot leg nozzle

SE-BL9-5 Bottom-longitudinal Brol<en loop, hot leg nozzle

SE-BL9-6 Left-longitudinal. Broken loop, hot leg nozzle SE-BL9-7[a] Left-45 degrees Brok~n loop, hot leg nozzle SE-BL9-8[a] Left-circumferential Broken loop, hot leg nozzle SE-BL27-l [a] South-longitudinal Between pump and steam

generator simulator

SE-BL27-2 South-longitudinal Between pump and steam

generator simulator SE-BL27-3[a] South-circumferential Between pump and·steam

generator simulator

SE-BL27-4 East-longitudinal Between pump and steam

generator simulator

SE-BL27-5 North-longitudinal Between pump and steam

generator simulator

9

TABLE II (continued)


SE-BL27-6 North-45 degrees Between pump and steam

generator simulator . SE-BL27-7[a] North-circumferential Between pump and ~team

generator simulator

SE-BL27-8 West-longitudinal Between pump and steam

generator simulator

SE-PC4-l Top-lonqitudinal Intact loop, cold leg nozzle

SE-PC4-2 Right-longitudinal Intact loop, cold leg nozzle SE-PC4-3[a] Right-45 degree~ Intact loop, cold leg nozzle

SE-PC4-4 Right-circumferential Intact loop, cold leg nozzle SE-PC4-5 Bottom-longitudinal Intact .1 oop, cold leg nozzle SE-PC4-6[a] left-longitudinal lntact loop, cold leg nozzle

SE-PC4-7 Left-45 degrees Intact loop, cold leg nozzle

SE-PC4-8 Left-circumferential Intact loop, cold leg nozzle

SE-PCS-1 Top-longitudinal Intact loop, cold leg nozzle

SE-PCS-2 Top-45 degrees Intact loop, hot leg nozzle

SE-PC5-3 Top-circumferential Intact loop, hot leg nozzle SE-PC5-4 Right-longitudinal Intact loop, hot leg nozzle SE-PCS-5 Ri ght.-4!:> degrees Intact loop, hot leg nozzl~

SE-PC5-6lbJ ' Right-circumferential Intact loop, hot leg nozzle

SE-PC5-7[b] Bottom-longitudinal Intact loop, hot leg nozzle

SE-PC5-8 .:Bottom-45 degrees In.tact loop, hot leg nozzle.

SE-PCS-9 Bottom-circumfe~ential Intact 'loop, hot leg nozzle SE-PCS-10 Left-longitudinal Intact loop, hot leg nozzle

SE-PC5-ll Left-45 degrees Intact loop, hot leg nozzle

SE-PC5-12 Left-circumferential Intact loop, hot leg nozzle SE-PC14-l[a] Right-longitudinal Steam generator inlet nozzle

SE-PC14-2 Right-45 degrees Steam generator inlet nozzle

SE-PC14-3 Right-circumferential Steam generator inlet nozzle

SE-PC14-4 Top-longitudinal Steam generator inlet nozzle

SE-PC14-5 Top-45 degrees Steam generator inlet nozzle

10

TABLE II (continued)


SE-:PC14-6 Top-circumferential Steam generator inlet nozzle

SE-PC14-7 Left-longitudinal Steam gener~tor inlet nozzle

SE-PC14•8 Left-45 degrees Steam generator inlet nozzle

, SE-PC14-9 Left-circumferential Steam generator inlet nozzle

SE-PC14-10 Bottom-longitudinal Steam generator inlet nozzle

SE-PC14-ll[a?Bottom-45 degrees Steam generator inlet nozzle

SE-PC14-12 Bottom-circumferential Steam generator inlet nozzle

SE-PC15-l North-longitudinal Steam generator outlet nozzle

SE-PC15-2 North-45 degrees Steam generator outlet nozzle

SE-PClS-3 North-circumferential Steam generator outlet nozzle

SE-PClS-4 East-longitudinal 'Steam generator outlet nozzle

SE-PC15-5 East-45 degrees Steam generator outlet nozzle

SE-PC15-6 East-circumferential Steam generator outlet nozzle SE-PC15-7[a] South-longitudinal Steam generator outlet nozzle

SE-PC15-8 South-45 degrees Steam generator outlet nozzle

SE-PC15-9 South-circumferential Steam gen~rator outlet nozzle

SE-PC'l5-10 West-longitudinal Steam generator outlet nozzle

SE-PC15-ll West-45 degrees Steam generator outlet nozzle

SE-PC15-12 West-circumferential Steam generator outlet nozzle

SE-PC18-13 Bottom-longitudinal Primary coolant pump outlet

SE-PC18-14 Bottom-45 degrees Primary coolant pump outlet

SE-PC18-15 Bottom-circumferential Primary coolant pump outlet

SE-PC18-16 Left-longitudinal Primary coolant pump outlet

SE-PC18-17 Left-45 degrees Pri·mary coolant pump outlet

SE-PC18-18 Left-circumferential Primary coolant pump outlet

SE-PC18-19 Top-longitudinal Priamry coolant pump outlet

SE-PC18-20[c]Top-45 degrees Primary coolant pump outlet

SE-PC18-21 Top-circumferential Primary coolant pump outlet

SE-PC18-22 Right-longitudinal Primary ·coolant pump outlet

SE-PC18-23 Right-45 degrees Primary coolant pump outlet

11

TABtE II (continued):


SE-PCl8-24· Right-circumferential Primary coolant pump. outlet

[a] Plots not includ~d due to signal failure.

[b] Plots to 1.0 second not included due to calibration problem.

[c} Pl~ts not i~cluded due to calibration problem .

. . : 1:2:

. ·.

IV. EXPERIMENT CONDITIONS

The parameters affecting blowdown loads for Experiments Ll-2, Ll-3,

and Ll-3A are summarized in Table III. For a detailed description of

the experiment configuration, operation, and conditions for each of the

above mentioned experiments, the reader is directed to References 1

and 2. The conditions affecting blowdown loads in the intact and broken

loops remain the same for the nuclear experiments as seen in the above

mentioned Ll series experiments .

13

~

TABLE III

LOFT Ll-SERIES EXPERIMENT CONDITIONS

Experiment Break Opening System ECC Pressurizer Designation Bre.=.k Size Break T~12e Time .!1P Injection Pressure

Ll-2 full[a] cold leg nonli na l high cold leg 15.6 break area (delayed)

Ll-3 full cold leg nominal low lower 15.6 bre:~k area plenum

Ll-.3A full cold leg nominal low lower 15.6 bre3k area. plenum

Primar:.' coolant temperature - 282°C

Primar:t coolant mass flow - 272 Kg/s

Nominal break opening time ~ 17.5 +2,5 ms[b] -

[a] Full break area corresponds to si~ulation of a non-communicative double-ended break of an LPWR main primary coclant pipe.

(MPa)

[b] Nominal break opening time 1s the e:<pected time interval for propagation of a full circumferential break in the main coolant pipe of an _PWR.

V. DATA PRESENTATION AND DISCUSSION

Accelerometer and strain gage data from Experiment Ll-3A are

included in Figures 2 through 172 which are included in total at the end

of this section. The characteristics of this set of data are similar to

those from Experiments Ll-2 and Ll-3,

accelerometer data from Experiment Ll-2

unusable due to nonzero average traces and

Ll-3 acceleration data to 0.2 s revealed

except in the case

which was considered to

spurious noise.· Review

ampl itu'de of acceleration

of

be

of

and

frequency content similar to the included Ll-3A acceleration data. The

strain gage data for all three experiments were reviewed to 0.2 s, and

it was concluded that the Ll-3A strain gage data were representative of

the strain gage data from all three experiments. Strain gage data to

1.0 s were reviewed since, in a few cases, the maximum dynamic strain

did not occur in the time during which ~ubcooled conditions existed.

Review and comparison of accelerometer data from Experiment Ll-3A

with predicted and design accelerat"ions, as summarized in Table IV,

indicates the following:

(1) In general the data are ~haracterized by a high degree of

noise in the form of preblowdown system vibration and/or high

frequency localized accelerations which are amplified due to

resonance in the accelerometers (Figures 5, 11, 15, 17, 20,

21, 22, 23, 24, and 25). These characteristics make quantifi

cation of the recorded accelerations difficult and highly

subjective.

(2) In many cases the low frequency (less than 110 Hz) amplitude '

of the recorded signal is estimated to be less than the

accuracy 1 imits of the accelerometer which is on the order of

,:!:0.20 G (Figures 7, 13, 17, 21, 23, 26, 27, 28, 29, 30,

. and 31).

15

(3) Some of the data are characterized by a shift in the average

value of the signal and/or are highly nonsymmetric which, upon

integration, would indicate unbounded displacements in the

system (Figures 6 and 14).

(4) With the problems in 1 through 3 above in mind, the data

review and comparison indicate'in most cases that accelera

tions in the frequency range less than 300 Hz are below the

predicted and design values. Accelerations at frequencies

greater than 300 Hz are believed to be local rather than gross

structural response and/or noise and give rise to deflections

less than 0.025 mm (Figures 2 .• 3, 10, ll, 12, 15, 16, 18, 19,

20, 21, 22, 23, 24, and 25).

(5) The measured accelerations at AE-PC17-l and AE-PC-17-2 (on. the

steam .generator, north s i·de) · exceed the LOCE design va 1 ues by

nearly a factor of twb. However, integration of the data

yielded deflections which were less than half those associated

with seismic_loads. Since the system is designed for combined

~eisMit and LOCA loads, tne LOCE loads will not pt~sent a

structural problem.

(6) The accelerometer data at AE-BL2-l (simulated steam generator

flange) indicate _that the measured .accelerations are slightly

higher than pre~icted and desig~ values. Integration of data

at this location yielded deflections le~s than half those for

seismic loads assuring structural adequacy for LOCE loads.

Review of the strain gage data indicates that the dynamic strains

at all ~easurement locations are Tess than 150 x 10-6 m/m~ The strain

data are characterized by a gradual: build up of. the signa 1 s corre

sponding to response to pressure relaxation during blowdown. Dynamic

fluctuations about the gradual build u~ correspond to response to

dynamic excitations, and the half range magnitudes a.re much lower than

those associated with pressure relaxation. The accuracy level of the

strain gage data is on the order of 10 x 10- 6 m/m which is 25 to 50% of

16

the half range magnitudes of the dynamic fluctuations. Since the

dynamic fluctuations are small (giving rise to stresses less than

1.12 X 107 N/m2) and not much larger than the accuracy level of the

signal, reduction of the strain gage data to component loads for

comparison with predicted data is deemed unnecessary.

In general, the magnitude and noise level of the structural

response data make quantification for direct comparison with predicted

·and de~ign values highly subjective. It is felt that the data are

applicable only to the LOFT facility oue to the complexity of the system

and are not applicable to LPWRs in general. Use of the data for

structural code qualification is not recommended due to the problems

involved in quantifying the recorded signals (low amplitudes, high noise

level). It is felt that the data can be used but should not be relied

upon solely for LOFT requaljfication due to the problems associated with

obtaining meaningful measurements at all critical structural points in.

the system (welds, joints, tees, etc.). A comprehensive inspection

program for welds and components at intervals based on fatigue analysis

will be included for requalification of the system. The present mea

surement system is deemed adequat~ for the purposes of LOFT structural

response determination and eval~ation, and additional insturments or

repositioning of measurements is felt to be unnecessary.

Hydraulic loads associated with nuclear LOCEs should be no more

severe than those arising from nonnuclear LOCEs since the system flow

rates for each case (assuming equal break areas) are the ·same. Decom

pression loads for nuclear LOCEs should be somewhat smaller than those

for nonnuclear ·LOCEs, because the saturation pressure in the upper

plenum is higher for nuclear experiments (11.44 MPa ·nuclear LOCE,

6.62 MPa nonnuclear LOCE). It is concluded that no major differences in

structural response data are expected in the data from nuclear tests.

Results of this analysis indicate the subject system is adequate

for LOCE loads and further analysis with structural codes is deemed

unnecessary.

17

TABLE IV

SUMMARY OF ACCELEROMETER DATA FOR EXPERIMENT L1-3A

Measured D~ta[aJ Predicted. Oe.vi ce ~q:e] era:t,i on., f.req_~.e .. ncy Acce 1 e.r.at.i on, Number. (-G). (Hz) (G)

AE-BL2-.1 0.7 30 0.6 AE-BL2-1[b] 1.6 500

AE-BL2-2 0.6 10 1.2 AE..:BL2-2[b] · 1.9 600 ,,

AE.- BL3-l[ c] data invalid 1.3 AE-B.L4-l[d] data invalid 2 .. 3 AE.-Bl,.5~ 1 [c] data invalid 2. 1

A~-PC3-1 0.2 20. 2. 1

AEi'H.C)::,J' 0.~ .12.5:' 2:,:1: A6-PC3.,.-l [b] 1.9 300

AE-PC3-2 ·0. 9 40 2. 1 AE-PC3-2[b] 2.3 300 AE~PC3,..3[e] 0.3 60· 2 .. 1 AE.,.PC3-3[b,e] 1.4 300> .

AE-PC6-1 ''l. 8 100 l.8

AE-PC6-1 [b] 3. 1 700 AE-PC6-2[e] 0.9 200 1. 6 " AE,.PC6-2[b,~] .· 4c. 2 '. 900 ·. ..

AE-PC6-3 0.8 40 1.8 AE~PC6-3[b] . 3. 2' 400

AE.,.,PC7-l· : 0.2 25 1; 4·

AE-PC7-2[c] '- '·data. inv·a1·id· 1.6 AE-PC7-'3[f]. '· .. data i nva·l id '1.6

AE-PC16-l[e,g] 0: 5· , .. ,. ·80. 2. 1 AE-PC16-1[b,e,g]· 1.9 1000

AEA·P(:1G~2 0.5 40 • • \I ... L2 AE-PC_l6-2[b] 0.9 300 AE-PC16-2[b] 1.2 s·oo

18 .

Desjgn Acce 1 e.ratj on

(G)

0.67

l. 63

·8. 60

4.86

5.55

10.8

1 o·.:a

13. 1

10:9

7.05

8. 54.

''. 2. 36

3. 00.

4.28

2.59

9:93

14.9 ·;.

TABLE IV (continued)

Measured Oata[a] Predicted Design Device Acceleratjon Frequency· Acceleration Acceleration .. Number CG2 (Hz) (G) (G)

AE-PC16-3[e,g] 0.3 30 1.0 11.3 AE-PC16-3[b,e,g] 2.0 400

AE-PC17-l 0. 3. 15 0. l 0.18

AE-PC17-l 0. l 100 0. l 0. 18 AE-PC17-l [b] 2.8 700

AE-PC17-2 0.6 25 0.3 0.34 AE-PC17-2[b] 7.8 1000 AE-PC18-l[g] 0.2 30 0.6 l. 79 AE"'-PC18-l[b,g] 1.6 800 AE-PC18-2[g] 0.4 60 0. 7 2.15 AE-PC18-2[b,g] 2.0 1000 AE-PC18-3[g] 0.3 25 0.4 3.57 AE-PC18-3[b,g] 1.2 600 AE-PC19-l[g] 0.2 100 0.6 2.08 AE-PC19-l[b,g] 0.6 400 AE-PC19-l[b,g] l . l 700 AE-PC19-2[g] 0.4 50 0.8 2.49 AE-PCl9-2[6,gJ 2.5 800 AE-PC19-3[g] 0.4 30 0.4 5. 77 AE-PCl9-3[h,gJ 1.3 4UO

AE-RVl-1 0.2 20 0. l 0.21 AE-RVl-1 [b] 1.6 - 350 AE-RVl-2[h] 0.3 13 0. 1 0.21 AE-RVl-2[b] 1.8 350

AE-RVl-3 0. l 15 0.3 0.42 AE-RV1-3[b] 2.0 350

AE-RVl-4 0. l 30 0.4 0.42 AE-RVl-4[b] 1.6 300

AE-RV1-5 0. l 13 0.4 0.42

19

/

'TABLE IV· (continued)

Measured nata[a]. Predicted Design Device Acceleration Frequency Acceleration Acceleratiop Number (G2 (Hz) (G2 (G) c

AE-RVl-5[b~. 1.5 300.

AE-RVl-6 0.3 100 0.3 0.42 AE-RVl-6[.b] 2. l 350

ral AccuracY of tabulated data is poor due to its low ma~nttude relative t.o no i s.e 1 eve.l .

[b] Acceleration believed· t.o be iocal and/or high level noise, not structural. as displacements are less than 0.25 ~m.

[c] Data have a bias zero shift and/6t the signal i~ highlY ·nonsymmetri c (.indicating unbounded displacements.).

[dJ Signal· appears to be 60-Hz noise. . .

[e] Data are high·ly questionable due to nonsymmetri·c characteris·t:ics.

[f] Signa]· failed.

[g] High degre~-of noise prior to tim~ zero has definite effeit ·on s-ignal· afte.r time zero, making resul.ts of data reduc.tfon. CJIIP.S t. i nnnh.l P.;

[h] Integration· of the data-yields de-flections whi.ch increase.- in magh-i-· tude throughout the: subcool ed b lowdown state i'ndi cat i ng -the data·; are invalid:

2.o.-:

.

2.0

0.0 ~

z: 0

I-«:

"' ...., -' ....,

-I. 0 '-' ~

-2.0 L-~~~~~~~~~~-d~~~--~_.~--~._~~~~--~~~

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE !SECONDS>

Fig. 2 Acceleration at simulated steam generator flange, East-West (AE-BL2-l).

2.0

!::. 0.0

r5 ;::: «: "' ...., -' ...., u u «: -I. 0

-2.0 ~~~_.~~&-~~~--~~~_.~--._~~~--~._~_.~--._~_,

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 3 Acceleration at simulated steam generator flange, North-South (AE-BL2-2).

21

:z 0

s LLI _, LLI u u <(

:z ~

Oo <( 0:: LLI _, LLI ..., u <(

500

2o5

OoO

-205

-500

-0°05

Fig. 4

·!50 0

2o5

OoO ...,.,..

-205

-500

-0.0!3

Fig. 5

I I

I l I •I• •

~I

II~ ~ \

l rn I --r

1rr r• -,

0°00 0005 0 0 I 0 0 0 15 Oo20

TIME AFTER RUPTURE ISECONDSl

Acceleration at simulated steam generator top~ vertical (AE-BL3-l).

A

~

• ~ • l 'I

A ,,

I IWII ~ ~ I

v lUll I I

•• 1 II II Jll'

II rr

i

OoOO 0°0!3 0 o I 0 0 0 15 0.20

TIME AFTER RUPTURE ISECONOSl

Acceleration at QOBV, cold leg, North-South (AE-BL4-l).

22

..

2. z 0 ;:::: g; ...., ....J ...., u u <(

z 0

s ...., ....J ...., u u <(

5.0

2.5

0.0

-2.5

-5.0

-7.5

-0.05

Fig. 6

2.0

I . 0

n.o

-I. 0

-2.0

-0.05

l .. ,,u I II ... Ia

~Yf n~r 1 ~~ H1 "''U!rlllll lA. 'II Ill

·n~ P' ~ Jl' If IU 't: lrrl "' rJ ' I r--

ll!:. " ']

II

wn w I'

0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONDS>

Acceleration at QOBV, hot 1 eg, North-South (AE-BL5-l). ~

I • II II Ill 1'1 r .l 14!J ~ 1. rt lA~ •t I• A -n:

.M -M ~ AI 1111 IV \IYV '\II ~ IUYI 1 ' l1 I' 1 .. ' H

r

0.00 0.05 0. I 0 0. 15 0.20


Fig. 7 Acceleration at 90-degree-elbow downstream of primary coolant pumps, East-West (AE-PC3-l).

23

2.0 1--1·--

1-·

1-- ••• r- I ..

I .!\. •• Rill~ l

I. 0

0.0

2-

~~"'" I

" IL I. , f Rl\ • I J

I ,, 1'\ l D 1\J, j ,

111111 I I Ll J l II .. I-· J"' PI I• 1-

:z: 1-0 -I .0 ;::: ~ i-UJ ....J UJ

1-· : u u ~-· ex:

-2.0 :--1 .L~t~. -·

--.. :--+- -· --.. _; --~-- -- : - ---·

-3.0

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TJHE AFTER RUPTURE !SECONDS)

Fig. 8 Acceleration at 90-degree-elbow downstream of primary coolant pumps, North-South (AE-PC3-2).

~

:z: 0 ;::: ~ UJ ....J

ti u ex:

Fig. 9

2.0 1·-

1--, __

I--

I . 0

-I • R~

IJ I Ill 11 0.0

11111111 ll '" ll I.Jh • .I.! IAI J ~ '"V ~ 1\M IIIlA J11 ·r N'-,M

IPI ' I 111 ' ., r I' lrl Ill r

1- - I I 1--

' -I . 0 e .. -- --.... -+---

·-·1--

-e.o i

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE !SECONDS)

Acceleration at 90-degree-elbow downstream of primary coolant pumps, vertical (AE-PC3-3).

24

...

e z: 0.0 ::: 1-<2: 0:: u.J ...J u.J u u <2:

-2.5

5.0 L---~~_.~~~~~_.~~~~~~_.~--~._~~~~~6-~~

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE ISECONOSI

Fig. 10 Acceleration at 45-degree-elbow in intact loop hot leg, East~ West (AE-PC6-l).

-5.0 ~._~--~~~._~~--~--~._._~_.~----._~~_.~----~~

Fig. 11

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE ISECONDSI

Acceleration at 45-degree-elbow in intact loop hot leg, NorthSouth (AE-PC6-2).

25

:z 0

1-

~ LoJ ---' LoJ

i t--+---' ' ' I

~--+-~-+--~~~~~~~-+-4~~~~~~H-~-4.-+-~-+~

~ -2. 5 ._ ____ ..,....-+--+-+-+-

-5.0 ~-----~--_.~ __ ._ ______ ~----------~--~--._ __ _. __ ~------~

-o.o~ 0.00 0.05 0. I 0 0. I !:I 0.20

TIME AFTER RU~TURE ISECONOSl

Fi·g,. r2· Acc·eler.ati on. a-t: 4-5-dE:~ree.-el bow. in intact loop~ hot reg., vertical (AE-PC6-3) ..

!3.0

-5.0 L-----~----~----------~--._ ________ ._ ______ ~ __ _. ____ ._ ____ ~ -0.05 0.00 0.05 0. I 0 0. 15 0.20

Fig. 13


Acceleration at 90-degree-elbow in intact loop hot leg, EastWest (AE-PC7-l).

26

-4.0 ~._~_. ____ ~._~_. ______ ._~~------~~~----._~_.----~

-0.05 0.00 0.05 0. I 0 0. I 5 0.20

TIME AFTER RUPTURE (SECONDSl

Fig .. 14 Acceleration at 90-degree-elbow in intact loop hot legs NorthSouth (AE-PC7-2) .

'(;' I . 0

z: 8 1-..: "" UJ _J 0.0 UJ u u ..:

-I .0

-2.0 ~._~~_.~--~._~_.~~--~._~_.--------~~_. ____ ~._~

-0.05 0.00 0.05 0. I 0 0. I 5 0.20

TIME AFTER RUPTURE (5ECON0Sl

Fiq. 15 Acceleration at primary coolant pump inlet, East-West (AE-PC16-l).

27

7.0

6.0

. 5.0

~ :z: 4.0 :::: 1-

"" "" ..... ....J

I&

J -- II ... I• A .. ... .. - 'I\ \. ...... ~ - .,. l lJ t _ .... _ •• T

-·- ·- IIIII I 'II ' I I

..... 3.0 u

u

"" - -t---1-· ---+-

I --+-2.0 . - -+-

---+-·-

··-t·-.... --I. 0

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONDSI

Fig. 16 Acceleration at primary coolant pump inlet, North-South (AE-PC16-2).

<.!)

:z: :::: 1-<(

"" ..... ....J ..... u u

""

Fig. 17

~.0

0.0

- I .o

-2.0

&3.0

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONOSI

Acceleration at primary coolant pump inlet, vertical (AE-PC16-3).

28

~ 0. 0

~ o< UJ --' UJ u u

""

-0.05

Fig. 18

:z: C)

1-

"" o< UJ --' UJ u ~

10.0

5.0

o·. oo 0.05 0. I 0 0. 15

. TIME AFTER RUPTURE ISECONOSl

Acceleration at s~eam generator north side, East-West (AE-PC17-l).

0.20

-10.0 ~~~~~~~~~~--~~~_.~--._~~~--~._~_.~--._~_,

. .-0.05

Fig. 19

0.00 0.05 0. I 0 0. 15

TIME AFTER RUPTURE !SECONDS!

Acceleration at steam generator north side, North-South (AE-PC17-2).

29

C..20

I. 0

~ :z: 0

I-<(

0.0 "" w ...J w u u <(

-I. 0

-2.0 L-~~~--~~~~--~--~_.~--~~~_.--~--~~~--~~~~

·-0. 05 0.00 0.05 0. I 0 0. 15

H ME AF"TER RUPTURE. I SECON.OS l

Fig. 20 Acceleration at primary cool9-nt pump l north side, East-West (AE-PC18-l).

I. 0

~

:z: 0 0.0 ~ <( IV

'" ...J w u u .:r I. 0

-3.0 L-~~~--~~~_.--~._.__.~--~~~_.--~--~~~--~~~~

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AF"TER RUPTURE ISECONOSl

Fig. 21 Acceleration at primary coolant pump l north side, North-South (AE-PC18-2).

30

~ OoO z 0 ;::: ..: "' UJ

ttl '-' '-' ..:

-I o.O

-200 ~~~_.~~~~~~_.~--~._~~~~--~~~-L~~~~~~

-0005 0°00 Oo05 0 o I 0 0 0 15 Oo20

TIHE AFTER RUPTURE !SECONDS>

Fig. 22 Acceleration at primary coolant pump 1 north side, vertical (AE-PC18-3).

~ z 0 s "' UJ -' UJ

'-' '-' ..:

0°0

-200 L-~~_.~~~._~~_.~--~._~~~~~~~~_.~--~~~~

-0°05

Fig .0 23

OoOO Oo05 0 o I 0 0 0 15 Oo20

TIHE AFTER RUPTURE !SECONDS>

Acceleration at primary coolant pump 2 north side, East-West (AE-PC19-l).

31

5 0.0

s .... -' ..... u u <C

-~.0 L-~~~_.~--~~~~~_.~----~._~~~--~--~._._~~

-0.05 o.oo 0.05 0. I 0 0. 15 0.20

TIME A~TER RUPTURE tSECONOSI

Fig. 24 Acceleration at primary coolant pump 2 north side, North-South (AE-PC19-2).

2.0

I•

I. 0

I

• 11 II ,

• l _.._1_1 _L

-~~~~1, 1, 11 • 11~ 0.0

I

-I. 0

I -2.0

-0.05 0.00 0.0~ 0. I 0 0. 15 0.20

TIME A~TER RUPTURE ISECONOSI

Fig. 25 Acceleration at primary coolant pump 2 north side, vertical (AE-PC19-3).

32.

-2.0 L-~~~~~~~-*~--~~~_.--~._~_.~--~~~_.~~._~~

-0.05 0.00 0.05 0. I 0 0. 15 0.20

Fig. 26

2.0

TIME AFTER RUPTURE ISECONOSJ

Acceleration at bottom of reactor vessel, west side, East-West (AE- RVl-1).

-2.0 ~~~_.~--6-~~~----~~--~--._~_.----~--~--~--._--~

-0.05 0.00 0.05 0. I 0 0. 15 0.20

Fig. 27

TIME AFTER RUPTURE ISECONOSJ

Acceleration at bottom of reactor vessel, west side, East-West (AE-RVl-2).

33

2.0

I. 0 J

J II II ·-

~ z 0

;: 0.0 "" 0:: LLI ...J LLI u u

"" • ~ I ~. v

"'' l'

~ llllr I I •

r-· I' P I 1

-I. 0

·---1'--

.-2.0

-0.05 o.oo 0.05 0. I 0 0. 15 0.20

TIME AF'TER RUPTURE ISECONDSI

Fig. 28 Acceleration at bottom of reactor vessel, west side, vertical (AE-RVl-3).

0.0

(;

"" 0

!;;: -I .u 0:: LLI ...J LLI u u

""

-2.0

-3.0 L-~~~~~~._~~_.~--~._~~_.~--~~~_.~--~._~~

-0.05

Fig. 29

0.00 0.05 0. I 0 0. 15 0.20

TIME AF'TER RUPTURE CSECONOSJ

Acceleration at bottom of reactor vessel, north side, NorthSouth (AE-RVl-4).

34

-2.0 ~~~~--~~----~--~._~~--~._----~--~~~~--~._--~

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 30 Acceleration at bottom of reactor vessel, north side, NorthSouth (AE-RVl-5).

.... 0

s ..... _, u.J u u ...:

I II I I

J ll-11 I I 1 t-o+-o+-+--+ .... tfl ~~ttlllllltHtnlttM kA lltl ~ ..a.1 ~ ..&.. ...r..... 0 .

0 J-+--+--+-t---iF-ifHflliiHfttlll H IWW ...._· r-+'-111.._.'__.+-'-1--+-___, .r--+·---i.., l--+--+---+--t---+--iH--1ffilltttt H r 1 r r II ..,

I

-2.0 L-~~~--~~~_.~--~~~~--~._ .. _.~--~~~~--~._--~

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 31 Acceleration at bottom of reactor vessel, north side, vertical (AE-RVl-6).

35

z -..... z -:J

z -< a: 1-Ul

100.

75.

50.

2S.

,, IIIII I .111

o. -0.05 0.00

I

II l

li'l~ lift

1nm II

I

0.05 0. I 0

TIME A~TER RUPTURE !SECONDS!

...J 1n1t

.I II IIJIIIU lftiiU. II 1'1 II

0. 15 0.20

Fig. 32 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-1).

75.

- -. 50.

z - 25 . ..... z -:J

- !1· y _j ... t1 J [l

I

~~ ll l1 1.11 II

r..l M I M I lllfll'l , ~ J'l I r II .. ~

" ~ I IIIII I [1 z o. - u I''J' < a: 1-Ul

I ltl~ ··--·· .. ···-··· ..... -······· --···. -·-··· ·-··--···-- -·-··---I \I'

-25. I

........ ··-····. ··-. ····-·- ·····-· --· -50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME A~TER RUPTURE !SECONDS!


36

75.

-50.

rtj ft

z -..... z

lo VII !IJr Ml 1 nl Ill 1\11 JV \ I~ lA vv

' • In -::::> 25. . .. . . , I I ~

I l z I ~ \ ~IJ -< a: ..... (/)

0.

I

A~ ~ II II JJ v '

"

-25.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE !SECONOSl


50.

I

0. A ~~ tit _u,, JU 'V ~ v ' r\11

• z liJ ... ..... z A ' '" -::::>

-50. al l\ I f\} II II l U' ~ \J v V\ ,J, 'I " j

""' II'\ (\j

z \IY ~~ 1f \ fJ I \ll \l -< v ~JIV \ I ~

,, 1/

a: ..... tJI lil 'l (/)

-100. v

'

-150. . ..

-0.05 0.00 0.05 0. I 0 u 15 0.20

TIME A~TEA AUPTURE !S(CONOSl


37

75.

!

• J ft ( II~

50.

'" A .z

' 25.

1n MI. ~ I

z -::>

N Lll II .....

z 0. -<(

- u II 'I

' -- ·rn II

a: 1-Ul

I w VI I

-as.

-

-!:!0.

-:-0.05 0.00 Q.05 0. I 0 0. 15 0.20


Fig. 36 Strain at re·actor vessel broken loop cold leg nozzle (SE-BL8-5).

z -., z -::>

z -<(

a: 1-Ul

150.

--1--

1 00.

50.

--

A.,

0.

··50.

-0.05

J .ru '

-·- .

l .l n tn 1\ v~ IJ1

~ UV' W\1 Y rr ' II' VI¥

I A

""' "' 1'1 ll "''I . I

I~

" J A 111n t\

u ~

. .

0.00 0.05 0. 10


11 f~ r \/ I I' M If u ~ ' &J ' I

,, 1

0. 15 0.20

Fig. 37 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-6).

38

100.

7'5.

z '50 .

z - . 25. <(

lr 1---(Jl

o.

-25.

_J_l l ~

··- ---

-----

-..

lA.

-0.05 ·0.00

n11 ·- -.. iJ. LJ !\J II I'

,.,_

fl II I

1\ f1 I

IV

..

0.05 0 .. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONOSl


75. -~-----1 I

I -------- --.. ___ --.. t-

'50.

z ... ~51 z

-·-- --I- f -----r-- M

llr -- f-- , II I' -- -- II v r '\

::J

z o. <(

~

11 II lr I-(Jl

~ ' I u 1

-25.

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


-Fig. 39 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-9).

39

!50. I I

100. r l. fi • It z t--

[I ilfl, ~- I!] ! l ru ......

z ::>

50.

,, v .n • ~ t--- rv ' ..

It z A <{ ~ Ia f\ a: 1- rr V' IJI

(Jl

0. ~ ~ . .. .

.. . ---50. I

-0.05 0 .. o 0 0 .. 05 0. I 0 0. 15 0.20

HHE AFTE"R RUPTURE <SECONDS l


!50. W--. .1

I

'· --

100. ... .. .. _j

,, z ll l~ li II I II

' r II u· I M v~ . z - 'l . . ' . ::>

50. ~ l

z -<{

a: 1-({)

0.

a I NOTE: Machine error in-Jl II ·n

processing data ~

Ill lA, ., plot.

' ,,

~ ·-·-

·~ ~- .. _

--··-

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



40

z ..... z ::J

z <C(

a:: lUI

50.

25.

0.

-25.

i I,! ! -·- rt-+-+-1--+--+-l--+--+-+---+-+--1----J-....1..--t- +-'-+---..

1-j . -+-+--f-1---.J-+ --+---+--+-1---+---1--+--+--J.-·l--+--+--+-!---lll-4!1-lft

~--r·-r-+--+--+-+-+-+-+-4~~~~~~+--~·+-+-+-+--+-~IA~~ I"'

I A Ill~ 1 u 1 ., ~ rw

II j N

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONDSl

Fig. 42 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l).

25.

0.

z ..... -2~. z ::J

= -50. <C(

a:: l-UI

-75.

-100.

'' .r

-0.05

n. 11 Ul Ill

111 'I

. -

0.00

. ~. JIIM Tm'l I II

~

~ I ~. Ia ~~ .,

1.1 T •' '"' • I PI\ ~ II l~ ;Tj ll IRI l "l l

IV II' 1W Ill ~, 'T IT 'I rll/1' I lUI _I

-- ...... -- __ .'' . ....

0.05 0. I 0 0. 15 0.20


Fig. 43 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2).

41

75. I I

f- :=J: --

50. ~ . It L z -

] Jlir n lTf Jll!IJ "' ~

..... z j " -:J

25. .II rn- r II

z l ~l a. II i -<( r-v ~,, II a: 1-til

o. I .A li ' 1~/

r; lu /VI r AI YV

1J II' ' v

....

-25. i -0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONOS>


150. i

+I i

.. • I J

I 00. I /lo AI .. 71 l~ r' ~ IV\. lafil ~ II\ 11 A n J\1 Ml rr 11 l v 11~ "J v 1

z -..... z

1 rr I v ~If I-

~ If -:J 50. A ~

n I lA

z l J IV 1

-<( {\ ~JV a: 1- A lA I II /It vI' Ill

0. I All Ul w.. lq " II --·

'\ ~ llf IU I'

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONOS>


42

75.

-- ,_ ----

·-- ·-

-----·

·--

50. u ·-· •• '1.1

z

' z ::>

25.

M ~ f-- -

w Ia, II II" 111 n 1 f-- -·--

IV tAi 1' vv I I all' I ~

z - l ~

<(

a: .....

~ ~ IN p

lll I~ u.

-

-25.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONDSl

Fig. 46 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) ..

100. --1--J.-.

-~~~-+= .. 75.

r- .I IJ IIA llU 1 J

z -~. '10. z

1--· ~

~

" -::> J II \ J.n [

t\1 ~ I ~--,,

-z

25. <(

I~ ~ A ll I. 1\.

a: ..... lll

llJ rt 1\ n ~ II , IJ

v I V'

0. v II 1

---25.

-0.05 0.00 0.05 0. I 0 ·o. 15 0.20



43

50. ! : ! ! ! I r-+-·· -+~ ---+-'· --·l ···-i ·- 1- -t- --r-- --·-c-~-

--+--j -·-+ --1- --r------ ·- ~-~-I-- ··- - --

--- ·-

o.

I 'V f-- -· -- --II .fl ' J

' I' ~l j ~ J

z

' z

\ 11 ~- \ j} /l ~ 1'1

·-~- - ~-ll. I~ 1\J U' ~INV

~ v J\, -, \1 'vJ ft A :::> -50.

z

- - -· lJ1

,.,, lW ~

--t 't I ~ v v

---r <t a: 1--~--1--lfl

-100.

--

-

-150. --

-0.05 0.00 0 .. 05 0. I 0 0. 15 0.20

Fig. 48

50.

25.

z o.

= -25. <t cc: >-1/J

-50.

-75.

TIME A~TER RUPTURE cSECONDSJ

Strain between pump and steam generator simulator (SE-HL27-2).

- ! .:-.1--~-:-~~~~= ~+=-- _-tt--~ --+--t--t-~f+--Jt-1- I-='=:= --+~--+---t---1 ---tl--- ~---t---t---- -+--- --, J " · ·- ·r--1·-- c-- 1 +-t-+--+--+--+-tt-t--ri'Mt-......,r-·-ftl-+---.--+-f----+--tt----1

I !

.J

1\

,

I - -t--1+-f-+--t---i--+--t---+--t-+-~~--+-+·-+--+-+--1--1--l---1

----1 I I I I I I

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONOSJ

Fig. 49 Strain between pump and steam generator simulator (SE-BL27-4).

44

'T

100.

l-

50. 11.. {

f\1 ~ PJ ' z

..... 0 . z

11\. ~ r \ .Jv. M ~. .I lA "" N _i

' ""V "'" "\-' tJ ~ 'J' \ I 1ft. v

''" 1 t

:::) \ 1 \ - - -\. ' z

-50. < a:

.J l"t ~ / lA

1-Ul \L

"11 ,.. l l ~

-100. V"t .I rw ~

- . ..

-150. I

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONDS>


25.

o.

z ..... -25. z

= -50. < a: 1-Ul

-75.

-100.

1\1 ID

11

-0.05

Fig. 51

~ I

!II

" L I

II II.. II .AI l , ftl ftftllrN

II J I . 'Ill ' II ' •• w J I .,

lll'lil I ••• I I PI rllll

Ji

Ill 'I L l

' II. Jll JW \a M

.I ll' I u ~ ~ I' I~ Ill

1'1

0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSCCONOS>

Strain between pump and steam generator simulator (SE-BL27-6).

45

25. !

·- f---

1-

" ·-

.J.

0. 1\J 11 n ~ ,, ~\ ~ .~

z. -'

If' I ~, u 1\

·u '\' . .li. Ill ..... z ·fl ~ -:::l

-25. I .. IJ ' ~la

"' IJ. [~ IV1.. 1 z j ' lJ 111 -< 0! , .. 1n

-50.

WI ~ IT ~A ~ . ~H. 1 "I . Ill I

~ fi·

' -75.

-0.05 0.00 0.05 0·. I 0 0. 1'5 0.20



--··- - -·~-... ·······. lJ II

0. ··-- - ....... ·-

Ill kl 1n l IW · ll 1~.

z I u ~

-. , z

... -·· - . ' ~-- .. .. . .

-~ ~' ~ -:::l -25. 'I I~ Ill !U

~ ft I,Aaj ~ .A ll ~ J z .A I~ " ~ ~I ~ I ru• l.!J. [11 -<(

0! ~

U)

-50.

'1'1 IUM \~ .

'Ill ·~ \II l

-

-75.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 53 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l).

46

40. I . I

: I 30.

I

20.

z -..... z I U. -:::>

~ T I ~ ~ '\I

1~11 :' . ..

~ II ~

..

~ z 0. -< ~ 0: 1-Ul -10.

-20 .

...,.30.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 54 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2).

150.

100. ~A \ .. ~ Ill ~~ IV LJ~ MY ,A . 'I A

"' A. '\I U\r ~ 'U j•l, r z - lNJ N . nJ Ill~ ~ .....

z -- -.

"' ~ ' -:::>

50. .Itt IM L ' z 1'1"\ -< a A I~

0: 1- JVl Ul

o. N A 11 . .. ll ~ ' ·~ _, r1 U\J ~

' l n

II

-!50. ..

-0.05 0.00 0.05 0. I 0 0. 15 0.20



47

z

z -<(

a:

""" l/1

75.

50.

25.

0.

-25.

-50.

-- --~-- --1-- ---i---11--t- f--··--- - -1--·- -+--+---+-- --l---1-f--l---+----l--+--J--+----l--+-+---+---l-+-+--+--1 - --+--+--+-t-1·- ··-- ·--f--+--l--t---11---f--+--+--l'---+--4~-+--l--+---1--f---l

---------f-+-~-4·-~-+--4---l-r--+--+~-~-+--+-+---l-f-+-+~---+--l

-- -- --+·--t----tt----1--t--l--+-~l--+--t--t---i-f--t--+---t-tt---fi--t---i--t--t--f

- -- - r-- -:---- --+-+--4-~-+--+--+--f--H--t--+-ttt-ft--t--+~-r----f -+-t---+--

1 II 11111 11 ll n 1\ II ~ U1 1.1

IIIlA v '" II' ,, ~ 1ft I ,. 1\

II II. lA

••

I

-0.05 0.00 0. 05· 0-. I 0 0~. 15 0.20

TIME AFTER RUPTURE (SECONDS!


I 00. --+- r· t- r---- ----'=+ --(-·~-- --·- 1----

---- r-- -- -75.

-- -II -

I j J'l --- --

50.

, .. 1'1 I \I' I I I --- II Ill

z -N JIJ A l\11 'II

' z ·~"~ Ill' r11 'II I

--,,

II lUI j :::> 25. llllUU

" lA iM" -Ill lA. z <(

a: 0. I-

" ~

en --' ---

-25. r-- ··--.

--·-·· ... ... . . -·.

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



48

~ tOO.

z -' z -::>

50.

150.

. ···-..+ ·--- --+ I ! --+--~-------~--- :---

~ I--+ 1 -! ll 1---1- - --1--- --

I (\ ~ n II II - --

1--~---- l I' II ¥1. II'' -r ,., \ft ll I ~ ~-+-- -!- "-ll \ I~ I

----~-i 1\ lA a 1 1----!--t--

M V UIIVI I

' I z IJ -<{

a: I-

I -,I 1.1 11'1 II

(/1

0. ~ IJI ~

f I

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE (SECONDS>


30.

f--

20.

I f-

~ l I. It l'

z

' z -::>

I 0.

z -<{

II J l'l ~ IU

~ ' 11M ~ IJf f--• ~ I

IMI I •• _,., , ._ I 'I

a: I-(/1

0. ~ I Ill

., . I"' I

-I 0.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFlER HUPlUR£ !SECONDS>

Fig. 59 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l).

49

30.

rl\ ~ .I

20.

Ml ... J ,~I ..... ILfll .J.J I(_ A. AJ ' 'IV y \8

.. .. Jl \1 !\... ,. w

~ z

~ M ..... z J 'l.t, I.M :::> I 0. tlJ ..

~ ' ~ I'

z I' -<{ r a: 1- ..., M (Jl

o. l wA .N I 'tf' l1' 'V "

II' . ·~ . ~

-10. . .

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 60 Strain at reactor vessel intact loop hot leg no-zzle (SE-PC5-2).

z ..... z :i

z -<{

a: 1-(Jl

50.

40.

30.

20.

I 0.

0.

··I 0.

-0.05

L

liMI

. .

r .. R. J JW '\W ..,..

r r'I'\.J .l"'l A.. .If , l .l. J(

#I ....,

I J ,... lt"

~ II

... I

I l J ,,

'\.\.

"'

0.00 0.05 0. I 0


I ...a r l!..

.f' rr'. \ i.J . ""' .... II'

0. 15 0.20

Fig. 61 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-3).

50

I 0.

0.

z , -I 0. z ::>

~ -20. < a: .... (f)

-30.

-'+0.

~-1--'--·· I---

lA.&J ~-

-0.05

.tt ~-- .., ~

.. Y\

1

.L J.. f"

IJ 1 J L / ... \1 L v IJ I\ fl

II\ -~ " I f\J 1\ .!"\ I, II 1r J J. 1

"' '11

----- -

0.00 0.05 0. I 0


-

,._ A I~ \ af \[

. ... J rv

' IJV v \1" 1\ •

\ J v

0 .'15 0.20


50.

_jj~ .. A J -.~. ... IN 1/W V\ ~ ~ t.t -··

·r. fi ~ 1ft' ~~ I" ,,. '+0.

, 30. z

·- , I

I ..... z ::> 20.

z < n: I 0. .... (f)

II -

l rv\ r-~~ {

1/

0. .tl . doth .l.. .J .. .... . ... "~V ~r·

-I 0. i -

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE rSECONDSl


51

125.

100.

75.

50.

25.

...... : 0.

I

! ·:

t ~ -v-;; -~. -· ... - - -

; -)!: ... ~: ... : ..... . ;;.;~· ..

-- ·t . - ~ -

-v~---:_·-· : .. ; . ~ ..

... . . -~- - .

• ,.-- . • + •• ··!· .... . -- ----·· ..... ····r -- . ···I-· . • .... .j.. -- •

-25. I

-0.05

Fig. 64

20.

I 0.

0.

I 0.

-0.05

Fig. 65

. ! . ~ .. ! --···:·- ··i·· ... -··- t.

' ~ - - ...•.. t

0.00 0.05

. -· ..... - ·- .... ···- .... I I

0. I 0

TIME AFTER RUPTURE rSECONOSl

0. 15 0.20

Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-6).

__.

-~ -- ··-. ----~----- _ _;_ ___ --- ...... - ..

-r- •.• ..; . --r --~-- ................... ·- ...

0.00 0.05 0. I 0 0. 15 0.20


Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-7).

52

'JO.

-- ~- --1---1-- ~- .. 1·- llr.AI La. 1111 ,.JlJftl'&

~- H~11lLJ ~M.. 1111. r ·, ,

'+0.

30. z

' z

.... • 1- L'llll ·' ·-f-• 1M. ...,,

• 1\_ .. T

:::> 20. .I •

• IL •• z ,,.... < a: I 0. 1- .. lll Ill'

..allr

o. I

'I" l,Jit" ~ .. ............. .,

-10.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONDSJ


'+0.

30.

z

'· ?0. z :::>

z I 0.

< a: 1-lll

0.

-10.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE CSECONDSJ


53•

25.

0.

~

" z

~ .. .tr~

-:::> -25.

z -< a: ... '/'!

-50. ·~ I""' I ' 'I

-75.

-0 .. 05 0.00 0.05 .0. I 0 0. 15 0.20

TIME AFTER RUPTURE ISECONOS>


50.

u 40.

30. z

' 7, -:::> 20.

z < 0: I 0. 1-(f)

o. ""'" '"'T"

-10.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 69 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll).

54

150.0

100.0 / ~ -r..-"

v z / .....

z -:::> 50.0 v

/ ~

z v <( I a: 1- / (/)

o.n v

-50.0

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE <SECONDS!

Fig. 70 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l2).

100.

-,~ \. It! ~ I 75. J - ,_

~ ,. \. ,}<.. /4r ....

1,1

z '· 50.

I 1/ ..

z :::> I

I v

z 25. <( I a: 1-(/)

J 'I If -·· -·"· .... ,~ ·-·· -·--

Q. r\ j

I'"\ J

·--- ~

-25.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 71 Strain at steam generator inlet nozzle (SE-PC14-2).

55

150. fWo A v !\.,

' 1/ " J i ,. \~ ~ ~

I 00. v ' .A. La

/ .., ~ -z - j

' z I -::::> 50.

j

I z 1/ -~ a: ~ I Ill

0. l.f

- .. .. . .. . -·-·· -~·· - - 1-

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 72 Strain at steam generator inlet nozzle (SE-PC14-3)~

20.

-

10. j 1·-- -

z ,,

-' z l -::::> 0.

z ,...., ~ a: ~ r.n

- I 0 .

M L. M I~ IIIII ,l W· l. I .jP' . ' ~ ,, 11 ., , fffLyJJ ., '

' I m I

-20.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



56

100.

75. r"r11L Jf \. ....... ,,...

WI .. ,.. Ia ..III 1_., , .. ~ n! "- ... .. ,,I"'

z

' 50.

I.a. rr 1' 1 .. 11 i"-" .. rrn z :::>

!If

• , z

25. r• <(

a: 1-(/)

I

' .. o. I. ... .. ,11-~

•p , •. IP'

-25.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE !SECONDSl


150.

tl' w ...,.. 'W T Tr Tr-""' ... """'

.,.

-" A

100. " If''"' IJ'

z -j

I ' z IJ :::>

50. 1

z 1/ <(

a: 1- J (/)

0. .... ,.

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTUR~ ~~~CONOSI


57

20. 1:·- " -J.

tA I 0.

., J I' I

~-· ..... z • li

1 '• ···~. -::::>

0. JIL

z -~ a: f-Ul

-I 0.

f'll ~ _. " " ~· ~~ lJ J..

A~ I II II ~ -I•' Ill I'"_L H ll • , ,. "' • •• u

U_J'I'" ' ,. l

'

-20. . -o,. o~. 0.00 0.. I 0,, 0 0 1,5 0-.20

TIME AFTER RUPTURE (5ECONOSJ


100. '

I '::J • .A

I/ ["\.,. ~ -- ---_L

--~

"""" 1/ v ~ ~ r-~

z :.r - 50. •.

I -z . ~

::::> .I ,. 1'

z 25. -~ a:

/ f·

f-Ul

l o. / -

.:'5.

-0.,. 05 0.00 0.05 0. I 0. 0 0 15 0.20

TIME AFTER RUPTURE (5£CONOSJ


58

200.

-

150. .,..~ _,... ~

~ v /

z -' 100. z ,I

:::> / /

z 50.

<(

I 1

a: 1-lll

I 1/

0. /

-50·- -. ~ -0.05 0.00 0.05 0. I 0 0. 15 . 0.20

·TIME AFTER RUPTURE lSECONDSJ


30.

'" AJI'I ..A J,j 11 \ Ia

20.

f4 \ " ' ,.,

I J \ r .,. z

·- I 0. z

• ,. ( 1\ 1 I L I \ I t"

A. , J " J '" :::> " I. I I""

.,. I - ·-

II ,.\ 11 I 1f 11 1,., ..

z ·o. <(

.J.. ·"'-ll' 'Wll "\

a: \ 1-lll "'I\. 1

\ r -10.

II I

-20. . -0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE lSECONOSJ

F·iy. 79 Strain at steam generator 1nlet nozzle (SE-PC14-10).

59

z

z < a: 1-Ul

z ..... z ::>

z < a: 1-Ul

150.

_,j. -r--

L.t. v 100.

I

50. J J

I

o.

1----l--+--+---4--lf----+--+--+--+--+----4-+--+-+--+-+-·· ·---- -·-+--+---i-t-+--1

' -50. ~._~~--~------._._._~--_.--~--~._~~~_.--~--~

-a·. 05 0.00 0. 05 0. I 0 0.15 0.20


Fig. 80 Strain at steam generator inlet nozzle (SE-PC14-12)~

50.

·'

40.

30.

20.

-·

~~ n ~

I .. J. _, ,·. ' '

" I~~ ~'-· f lJ· 'I "l ~ IV w I' :~. ~I~ fA

A~ ..

~ '1'~

I 0.

o.

~- '" ~ ~ ~ll I ~

:

J "V ·v ., . hi'NM 1'~1\11-

.

II

-I 0.

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME kFTER RUPTURE !SECONDS>

Fig. 81 Strain at steam generator outlet nozzle (SE~PC15-l).

75. '

•• 0 II ~~ ~ I m1 lA I. I '11

Ill "WI ~· '\ 'IJL.J 1 J. J' 1 lll"'f

50.

"' ~ M I

z M \ -·- 25. z

II laJI -:> rv

IJ

z o . ... <{ II .It • a: 1-lll

-25.

.... , Ill m M iii p• n n II rf

II r r1 I'H fl I

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 82 Strain at steam generator outlet nozzle (SE-PC15-2).

150.

1--A

~ J.j f\ I ~~ lA1 1'1..& ll l

~ IN. ll ~ ., W'l 11 I .. Y I'V' r(Jf

100. L /Y II .N~"

z - " u~ h. 1 r T ' N 1

' z ' -:> 50. AN'

l/ z -<{

a: 1- J ,}J lll

0. Ia A lAfi ~~ u I I V 'j r vv ' rv 'V' ~· .

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


F1g. 83 Strain at steam generator outlet nozzle (SE-PC15-3).

61

60.0 . .. - .. '

f--

50.0

40.0

z ..... z 30.0

::::>

l ~

,M .. ·. ~ A J

~ ' - .

z 20.0 -<{

II IJ IM~ ~ 11 r• ~ a: r-\1) I 0. 0 _, ....... ... '··"'

0.0 .. ·-··· -- .... -

-10.0 - -:-9-Q!:? 0.00 .9·9? . 9. 1.9 0.20

TIME AFTER RUPTURE !SECONOSJ


100. .

·- ----

7!'1.

. I II AI

z ..... 50. z ::::>

lA 1\ It II ~

"" I' I I IJ I Ll Ul " I I I Ill U' l.n Ill I "'I t ~ V¥1 , \J v l

r II 2 25. -<{

.J v IL ···•···

" ' a: t-Ul

a1 II II " IJ If U1J I' 11. L!.llll r

0.

... -··- -·-··. "I IJ 'r ·--- ... . .

-- ... .. ·-.. -· ..

-25. f---

I

I .

-0.05 0.00 0.05 0. I 0 0. 15 0.20



-: ...

z

z < a: 1-(j)

z -' z -::>

z -< a: 1-(j)

150.

- - ·-- --

---f-·

t\ A ill ~ u,.. n 100.

J, f.tl 1 I If iJI. I '\II ~ lM l'U Mf ~ 1\ ~ft u ' v

"V\1 .I I ' p IV 1\4 VI v

- 'I v t\IJ II -- -

50. A I' n rv - -¥

- .. - .. ·-I ,I AI

o. .A Jl riA , l 1 lV" VI If I ~ VII' ll' .. '

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fi~. 86 Strain at steam generator outlet nozzle (SE-PC15-6).

150.

100.

50.

~-l-+- -- --c--f---t-t--tf----1-t- -t---+-t--t-t--1--f---t- - --1---t--t---i --1-- --·- :._ --t--+----+--t--f--l--11---f--i-tt--1--f--·-t-- -t---t--t--t-t---t

f-f-- -- 1-+--t-+-+-+--t--t---+--t---+-+-+-+-+- +--+--t--+-+--t--t--1

I

-1--~-~-+~-+-+~~~~~~'H'~''ILb-~~f--i-t-t~-t-t--t--t~ -~---~-~~~ll~l~~~v~~~~--~-~~-~;--+--t-~-+ ~~~~ ·~~~._~N~~~V~I'-t--+--+---+---+--1--+--+--+-+-~r-r-r-~ 1l I / I

J\11 I 1\.A. 11 0

. II rl . ~

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



63

z

' z ::::>

z <(

a: .... Ill

z

' z -::::>

z <(

a: .... ln

200. - .. ~ ~-. - -.

-- --j-- --. -· --- -- --·--- -- 1----- ---

-···-·-I __ ·-

,. II t! I 150.

lJ lt .Ill!_ ~)j r1 -~ It\ II\ ~\ VI 'V V\1 --

I 00.

A I ~ v ' f-· Jll 1.111'

II V ),. 'V l-1 I~ IV I I r'V ~

A N 50. A

Ill

' I ,; a

o. lA II riA I Ill I. IJIUliiA lA 1 rv

IU II n 'I ~~ I' tf I'

f---50.

-0.05 0.00 0.05 0. I 0 0. 15


Fig. 88 Strain at steam generator outlet nozzle (SE-PC15~9).

ISO.

I 00.

J .. -~----1~+-- I I __ ,_ I -- L~--~-+-- ·-f--+

i : l_j -- -t -·t -··r--i ,---t··t·-r- -- t-·

~ ! !

-+t·-f-- v ~ ·---i-- ~ I~ ····-f-- I

ill

~ 50 .

IJ IJ

~ ~

-0.

-0.05 0.00 0.05 0. I 0


I J I

~ r

.l I~ M ll '~ w ' l\

0. 15 .

u '


64

fl\1 y

0.20

l ~~

0.20

..

150.

'·"" 100.

z - J ~ ' z r\ ,

' -::'1 5U. II t'l M_ II II 111 ITR

V I~ I VI \\ v ~\j y \ z ~ ~

.. -< a: 1- I N (/)

0. J 11\ lA IW

f f

-50.

-0.05 0.00 0.05 0. I 0 0. 15 0.20


Fig. 90 Strain at steam generator outlet nozzle (SE-PC15-ll).

150.

100. 11 j Ill I N

"' z - IV I r \a Aa "' ' z

........ ·--· ........

'I I~ l -::> 50.

Ill z ll -< II n a: 1-(/)

u. rJ lA [1

II ~

-50. ..

-0.05 0.00 0.05 0. I 0 0. 15 0.20

TIME AFTER RUPTURE !SECONDSl


65

I 0.

z - -·I 0. ' z

I

I I

I II IU II' 1n

I I

:MA.~ f.' I .. I II 1 .I.

... 0.

-::>

z -eo. -<(

v ~

I _l

IIIII lUI

-I 1111

~~~ ~,~ 1'11111 ,11 'II ,.,, II IUW

IIIU II 11'1 II; 1-

II' I f 'I r ' (fl

·30.

-'+0.

-0_. ('!:5. ('). 00> Q. 1u; Q.20


Fig. 92 Stra.in at primary. coolant pump outlet (SE-PCl8-l3).

5-0.

0.

z -a.l.u IJ

~ .I -~

\ ~~ fl'l IV .I • u·v.. ' z ' ,, rl -::.

-tiO. I

~ 1 f\J

z ~' -~ -<( I ·'I: VI ' I 0:: 1- ~ l'j ~- J ' ~ ....

·" Jl, •. 1/l

··I 00. ' 'IJj ~~ ~ ~ Vl ·n ~\ mn ~

" I' '

-150.

-0. 05· 0.00 0.05 0. I (J 0. 15 0.20


Fig. 93 Strain at primary coolant pump outlet (SE-PC18-14).

66·

50.

---f-~-+-1-- --+ i

--~---1--

-- --·t- I - ·-,_

- -i .. ·-

M 1\J. A 1.\ II\ A 0.

, l v '

'~ " "Vl z

' -50. z

Ll\a Y' V'\

I --;:\ \

"\I\ --'lA

z -100. -< \..

'" U\ a: 1-Ul ' W\!A.

' ., 1M. \ ... hAf .r IJfl.l I'\ ~ J\. ~ l1\

-150. ' I'V 1 I •• r IV' v ~

I

-200. -

-0.05 0.00 0.05 0. I 0 0. 15 0.20



25.

1--~ I

0. ! 'I n 1 I z - ,,~ \.U ltV M ....

z I PJ' ~ - ., ;:\

-25. llry

z . -~ LA -< , ~ a: 1- IY l Ul

-50. , ~~~~ I I v ll " ·~ ll'~ IM. ..... 1.\ II'

II ~ ~ \II tr'~ ~-'II/'

-75.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



67

z -..... z -:>

z -<(

a: 1-(j)

z -..... z -:>

z -<(

a: 1-(j)

25. - - b--t-

0. l 1

ll t ~ lA II -· II I'M IV\jj rltl.l 1 f11t ll

-25 . L 111 1.1 I .u :

v .

I L

-50. \II \1 It I

ru aft I • ~IL ~- N Ia.. l, 1\t. lLMI

lftll \1 \ ,, lJ l.nt f\ , .. !

-75. n r I n· _! 1'-'i II' : \A t-- .......

lJ

~- ·~·--- .... .. ··-~- -·~-·· ---....... _ u •• "' -~ -· ·····--1-

-100.

-0.05 0 .. 00. 0 .. 05 0 .. I 0 0. 1.5



50.

0. j

:1\l

-50.

-100.

. 150.

-0.05

na ·" ~I U\ ~,

I

.A rv~ 'VII I A

V\1 WI v A :Ju '1"1

~an \~ !\.. Ill

" v u .& 1n ... r W' ~\ r\ MJ liVIJ

y VI

0.00 0.05 0. I 0


LtJ l AI\ I

II' J Ju 1 '¥ n ' ·v u v . ' IVY

0. 15

1\ v

Fig. 97 Strain at primary coolant pump outlet (SE-PC18-l8).

68

0.20

.. l

lf1 I .

~ 1/.

' 0.20

50. · I 1 -·-·:-----r--r-r

---:-·- i ·-·- ·--·-•u-•t•·-i- ··--1-+

25. .. f ~; II. I UY I II II

0. z Ill lllf

"\\I lVI II

' z :::)

-25.

I Ill Ill

rC .II

z 'I II~ ll .A

UJII II IJI II A..l la lA. <(

a: -50. .... lll

" ,, ll_ II"U li'j _._. l_"' !LV

IU 'V U'~ Ill. I I ' ·u lJ

' II 1-

-75. --··

-100.

-0.05 0.00 0:05 0. I 0 0. 15

TIME AFTER RUPTURE lSECONDSJ


50.

0.

z ..... -'50 z :::)

~ -I 00. <(

a: .... lll

-150.

-200.

! ' -··-·r--- --· ··-·~·--·

I

-··-i·-H

l,J l n. I l~ lrl v•r

--

---t -

I

--I _:

-0.05

.A lVI a.

• ~. II -'' v 1JI t--,. '1 ll

'\J II..,

lall "" ---'ti1A

v [1. II 'I\. II n

v hi' J\ .A. _h \.l IJ.. r ., _V ~· \ 11\r\t Ml.l \ II '\I I ll\IV ~

' ~ Vl 'I 'V w '

\A. ,/ ll[

,.

0.00 0.05 0. I 0 0. 15

TIME AFTER RUPTURE lSECONDSJ

--

Ia. llf

II

0.20

_,.,_, .....

fi II I

II IJI T i

0.20


69

25. 1 " I I I I

I

I J. 1ru I~

0.

II II' Ill I I

z v u ~· !J 1\.ft._ -' .... -25 . z

> ~ i~ 1 'L ft n I A 'I /\~

::) u II " ' N I )j iiJ ]j

I ' z -50. - t II

< 0: 1-(/)

. '---r-· -75.

-100.

-0 .. 0,~· 0. 00. Q. 0.~ Q,. 10.:: 0. 1·5, Q·. 2.0


Fig. 100 Strain at_ primary coolant pump outlet (SE-PC18.,.22).

50 .. ---

o, I -- -

II\ I 'I I r 11

z -IVLWVH

IV ~ ..... z .~, -::::>

50.

z

II U1 l

·- ~ .' -~ V1 ~ A. . ~~-\ ~I IJdi·- . . ~j . Wv ft ·~ .I -< ·. lA/ '\1 ' I ~~-A, ' ~ lA

0: 1- tV 11\J w w (/)

-100. ' ' II u

-150.

-0.05 0.00 0.05 0. I 0 0. 15 0.20



50.

0.

z

' -50. z ::>

~ -I 00. <(

a: ~

lll

-150.

-200.

: : I I -f-L - t--··r- -r---~ -- ··i=- ~r-~- ·- ·--+--c-

wv ft/ II I IV lit IV\ I I

v ~IN 'I'

LA V' -

~-tl ~: ,- -

±-· -

' .I -·

'

r.

J '\ v 'II Vll. II I

•IJJ' ll tll ll lA [\A I! A

IV \I~ /'U J!W MJ IUV ., y ' l u ~ ' '\

-0.05 0.00 0.05 0. I 0 0. 15

z

' z =>

z <(

a: ~

lll



100.

7'3.

50.

25.

o.

-0. I 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


,,.. u

0.20

I. 0

Fig. 103 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l).

71

75.

50.

z .... 25 . z :::>

z 0 . .....

< a: 1-Ill

-25.

-50.

-0. I 0.0 0.1: 0.2 0.3• 0.4 0.5 0.6 0.7· 0.8 0.9 I. 0



75.

50.

z .... z :::>

25 .

• < a: 1-Ill

n.

-25.

-0. I 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 105 Strain at reactor vessel broken loop co.ld leg nozzle (SE-BL8-3).

72

z ..... z ::J

z <{

a: ~

Ul

50.

0.

-50.

-100.

-150.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

TIME AFTER RUPTURE !SECONDSJ

I. 0

Fig. 106 Strain at reactor vessel broken loop cold leg nozfle (SE-BLB-4).

z ..... z ::J

z <{

a: ~

Ul

75.

50.

25 .

o.

-25.

-50.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I. 0


73

150·.

I 00.

z ..... z ::>

50.

z <{

a:: ~ lJ)

o.

-50.

-0. I 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 108 Strain at reactor vessel broken loop cold leg nozz,le (SE-BL8-6).

1 00.

75.

z ..... 50 . z :J

z 25.

<{

a:: ~ lJ)

0.

-·25.

-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 . 0



74

z

' z :::>

z <(

a: 1-Ul

75.

50.

25.

0.

-25.

-50.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

TIME AFTER RUPTURE lSECONOSJ

I. 0


z

' z :::>

z <(

a: ..... Ul

150.

100.

50.

0.

-50.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I. 0

Fig. 111 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-ll).

75

z ..... z ~

z 1(

a: I-1/l

150.

100.

50.

0.

-50.

-0. 1 0. 0 0. 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0

TIME AFTER RUPTURE CSECONOSl

Fig. 112 Strain at reactor vessel broken loop cold leg nozzle (SE-BLS-12).

50.

25. z ..... z

,J,. J

" ,.,, ~

j; Ht II

-<{

a: 0. f-Ul

1-·

-25.

-0. 1 0. 0 0. 1

M .. j,, , I • lj

I ''II L.

r• II rr·, 'WI

---~- .. -·· ...... .. ··----- I····-.-· .. ·-···

II'

_,. ;

'

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


h~ ~ rr .. - ······-

1. 0

Fig. 113 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l).

76

25.

0.

z ..... -2~. z :::>

= -50. <t ._.

-75.

-100.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9


I . 0

Fig. 114 Stratn at reactor vessel broken loop hot leg nozzle (SE-BL9-2).

75.

50.

z ..... z :::> 25.

z <t 0::: ..... l/)

o.

-25.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9


I. 0


77

z ..... z :>

z <(

a: 1-(/1

150.

100. ''·~ IJ Allft. 1m''' I I I ,. I IIJ 'II II '. Ill I I II ,. l

' 'II I' r-

Ul

50.

II ' ..

0. D.ll "fHJ ..

I

- .

-50.

-0.1 0.0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 I .0



75.

50.

z -..... z -::>

2!J.

z <{

a: 1-(/1

0.

-25.

-0.1 0.0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 1.0



78

100.

75.

z ..... 50 . z :::)

z 25. -<

a: 1-lll

0.

-25.

-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



50.

II.~

0.

z ..... z ::>

-50.

z

I 'Iii Ill •• J I I I IJ .1 I '• 1 I I I

• II

~

I ,.1 I .......

'R II ' I I Ill II

< a: 1-

II I'

lll

-100. -·

-150.

-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



79

z ..... z ::::>

z -Cl a: I-Ul

50.

25.

o .

-25.

-50.

-75.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I . 0


100.

z -..... 0 . z ~

::::>

:z= -50. < a: f··· ...

Ul -

-100.

-150.

-0. I

II

-I A

.u I I " ,,

LAo!. lJ\ I.J r ..L 'I'

'M ' II\( r .1 ... ~ I

' 1 , .L _p !L\ .... !1"11'1 J ltru ,. w J t 1'1"

jJ '" "l.. II( "ln' I' 11 •c,_.,.f.,,. .. "" .~

II A. v tl • 7" ~ •

l1 r " l IU

\ .1. .. ..... Y.. 11 \1'1

-....... ~-...... --- ···-·--······ ·-·-··· . ··- ···--- ··---~

. -·· ··----~--- ·---

... --

.. ..

0. 0 0- I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I. 0


80

25.

FW L: -r

" ~· 0.

z I I -- f- ---..... -25 . z IUt J J I -::::> I fl

It I u J •• J..l I I II z

-50. -< a: 1-Ul

IJPI ~ I

I fl ---, I

" I r 1 I p

I J I

-75. II ' II

-100.

-0.1 0.0 0.1 0.2 0.·3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



25.

0. l.t

HI .I

I I z -..... z -::::> -25.

z -< a: 1-Ul

-50.

''II I. I "T JUT J li =II ~lit t

'1 l

r il I -.1 II

lfllh liU Ul r.l IWII illftl r1 '"''

'( If I • • ~ lfll' I

I

I' 'I Jl T

-75.

- 0 . I 0 . 0 0 . 1 0 . 2 0 . 3 0 . 4 0 . 5 0 . 6 o·. 7 0 . 8 0 . 9 I . 0


Fig. 123 SLr·din between pump and steam generator simulator (SE-BL27-8).

81

z

' z ::>

z < a:: 1-Ul

25.

0.

-25.

-50.

-75.

-0. I 0. 0 0. I 6.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9


I. 0

Fig. 124 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l).

z

' z ::>

z < a:: 1-Ul

~0.

30.

20.

I 0.

0.

-10.

-20.

-30.

-0. I 0. 0 0. I 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9


I. 0


82

150.

I I I

100.

z ..... z

~~ .1 ,~ 1 Ill II

~I I I JJ I I I ' ::::>

50. II IP

z <

"" a: 1- II (/)

0. ~~ Ll

-50.

-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



75.

50.

z ..... 25 . z ::::>

z 0.

< a: 1-(/)

-25.

-50.

-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



83

100.

75.

I

50. z I.

• ..... z ~111 1 :::)

25. 1.1

• • II

z < 0:: 0. ~

lll Ml I

-25.

-50.

-o. 1 0.0 0. I

1 I

1 I I I 1 .. I. w Ll. _l

L lh _l ,u Ill lit .. 1

• IW L II I I LU

111 I III I 'I' , I

111 n ''1 I J _r: Ill I t II I I I

I I

.. -

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


II I'

~

--

I. 0

Fig. 128 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4~7).

z ..... z :::)

z < 0:: ~

en

I "in

100.

50.

o.

-50.

-0. I 0. 0. 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I. 0


84

30.

20.

z -' z -::>

I 0.

1 ~ 1 I llll

~ All II ,,

z -c{

a: 1-lfl

o. =i1 I ,

-10.

-0.1 0.0 0.1 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0

liME AFTER RUPTURE !SECONDS>

Fig. 130 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l).

30. -.

20. ' Nloll.l .at • ~ .J I .•• J. J ... ..,j ~II J Y'l'll1V1 ~ IT .,., .. . NPwn1lf ~M

" ~ . ~' . , r " J • 1 J r J .. ~

r I ' z - ' ' z -::>

I 0.

z -c{

a: 1-lfl

0. .J.J 'll'l

'

-I 0.

-0.1 0.0 0.1 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0



85

50.

..a Ill ... 1t.U1 .. J.At ....

~ -~ 1'1J,.. ..o& • • .II. Jll,. ..

,flll"' l.f ll/~..11 ..llll 1111n J ~ lr I .1"\Jf\1 ~ liU ll''Y .. Ill • ' 1.1 ' lll I .... (_l_

' 1__)1 !I_ ll ' _I_ v ' '

40.

..... ' • r I I' 30.

z nr _I

• ' z :::>

20. II f

J z " <(

a: I 0. 1-Ul

·- ..

•• 0. .. " J. ..... ... --- ...... . . , .... -

_ ..

·-. .. .. ..

-I 0.

I ·-·

I .. ·- . --

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0



1 n.

0.

z , -I 0. z :::>

~ -20. <(

II. II/)

-30.

-40.

-

-0. I

.M

·-

I Ill If

0. 0 0. I

--

..

-

• .. . .L •"' l.ll.L ..... ..... ..... ......_~ ........ r'V'P- IIYaaJl '-' 1"' I r .:"'"' rtl..,.....

-·J~~n u-.... ~ '" T .., 11'1 ~ " . . .1' II'

I ' . -- .

. . ·····

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 133 Strain at reactor vessel intact loop hut leg nozzle (SE-PC5-4).

86

50.

' .. • .. ... • .. I • 1 J ....

j~F·.,."'" 1 .. ..,....,,.... ,, ....... "'""'"'· t ,..,.,, " .. '

I~ r • 40.

30. z ...... z :::>

20.

z N < a: I 0. 1-Ill

0. .......a.! "T'l

-10.

-Q, I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 134 Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-5).

50.

40. 1

30. I z ...... z ul ,.. :J 20.

z I < a: I 0. 1-Ill

1

0. ...... T'T

-1 ·a.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.~ 0.6 0.7 0.8 0.9 I. 0



87

z

' z ::>

z c{

cr >-IJ)

40.

30.

20.

I 0.

0.

-I 0.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

TIM~ AFTER RUPTUnE !SECONOSI

I . 0

Fig. 136 Strain· at reactor vessel intact loop hot leg nozzle (SE-PC5-9).

25.

f--

u.

z

' z ::>

-25.

z -c{

cr >-1.0

-50.

f--

-75.

-0. I

.Ill .oil

n I • I J

0. 0 0. I

--

--

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


I. 0


88

50.

' 40.

30. z ..... z :::>

20.

z <(

0:: I 0. 1-Ul

0.

-I 0.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I . 0


Fig. 138 Strain at reactor ~essel intact loop hot leg nozzle (SE-PC5-ll).

150.0

··-··--- ··-------f----f- ---1-----+---+----f----~'-----f -·--.f-----1

----··-··· ··--·--t-·-----1~----t---+---+----+---·-f-·--+---+-----1

-----····· r------- ------t----t----ff----+---+----.f-------1r-----t----t

r .,

100.0 .,...,..

z I I .....

z I :::>

50.0 1 I

z <(

0:: 1-Ul

1 ---~~---- ---+-----r--~r--~--~---~--~--+--~

I

0.0

--·-- --·--~--1---+---r--~t----~-==-+----

--~------+--- ~--~--r--~r---~---+-- ---1--~

-50.0 ~--~~--_. ____ _. ____ ~----~----4----~~--~----~----~----~

-0. I 0. 0 0. I 0.2 0.3 0.4 O.!:i 0.6 0.7 0.8 0.9 I. 0



89

\ .

z ..... z :::>

z ...,. 4: a: 1-(JI

z ..... z :::>

z 4: a: 1-•n

100.

75.

50 .

J I'

25 .

...

:J.

~·-· ....

-25.

-0. 1 0.0

~ A. ... _.... 1 !A ..._ .. , "' /Ylll ll~ ... .....,.... -v -. I"" """

Jll\ , ' I .....

j f

; 1

0. I

I IMJ

'.J

. ., .. .. . .. . ... -- ....... _ ···- .. -- --

..... ··- .

-

0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9


.._

I . 0


150.

1 uo.

50.

0.

-50.

-o. 1 0.0

I

I 'l -

I

' 1 I -~A -I

(

..

0. I

"\. IJ.J - """""' ...... ~

.,~

·-·

--- .. -

0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9


.,

·---- .....

-·-

I . 0


90

20.

I 0.

z .... z :::>

0.

z < a:: ~

Ul

-10.

-20.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I. 0



I 00.

~ _...

·~5~ .... ..,., ............ I'll j ... r.,... ... 1 ~

75.

z .... 50 . L

~ ... ~ ,

:::>

z 25.

< a:: ~

Ul

o. ....... ,. ......

-25.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I . 0


Fig. 143 Strain at steam generat~r inlet nozzle (SE-PC14-5).

91

z

' z ::>

z ~

<(

a:: I-(/)

z

' z ::>

;z

<(

a:: !-(/)

!50. I.... . ...

liW" ........ ....... ..... .... ...- .. ....,.. ----

' ,

I 100.

, I

50.

I I

0. -~~

.... ...... .. - .. ·- ...

-50.

-o. 1 0. 0 0. I

- .. ~-- ... --- -·

.. - ~-

·- --

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9



20.

·-

1 a.

.1

0. ~ J

I. 0

-I 0. ' I .. ] ~ ~ • lliR ~_..... rr .l lf ' '

" _, ' ill

-20.

-0. I 0. 0 0. I

1 ..... I r ._ ,

. . ·1---

0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 145 Strain at steam gener'ator inlet nozzle (SE-PC14-7).

. 92

"

I . 0

z .... z :::>

z <(

a: 1-Ul

z

' z :::>

z <(

a: 1-Ul

I 00. --·

··- ---- f-·

I"" ... .-r J '

,...,..... ~ ,J I'... F .. ._. ~ .-..... 75.

I I' I _,

~ ...,.,., ~

I \IV" I

50. 1 I --1 r I

-

25. (

I ...__

o. .-..... .l

-25.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0:7 0.8 0.9 1-. 0

TIME AFTER RUPTURE' <SECONDS!


200. ------ -----~----4-----~---4~----t----~----4r----~----~--~

---- f--·----+------t----------1----l-----+---+----+-----t----Jf----t

150.

I ... !

I 00 . I l I

r----~~---4----~----~----~----+---~r--~----+------t---~

.50. ~-----~~--~---------1-----+----~---~---+-----t-----Jr---~-----1

. 0. I

~--~-----+----~----~----~---~----+-----~---4~--~----~

-§0.

-0. I 0. 0 0. I 0.2 0.3 0.4 o·.5 o.6 o.7 o.8 0.9 I. 0


Ftg. 147 Strain at steam generator inlet nozzle (SE-PC14-9).

93

30. ,-----·- --·-- ----·. ·--- ---·-· f------ 1----- ..

al 111 ILl ft. .,'L .J..JLII .. ~ ........... •IJA IU J r~ \1 l.t ,.J wn. 11.,. 'V ,.,.. ... .. , .... II ..... ..., 20. , l -J ll"J v ........ ' fT "1

-- •fll' .LII '1 z "r r ..... I 0 . z ·' ·'

IIIIJ ' ::l

l'l 1111 v

z 0.

<t

........ 1--

., " --a:

..... f--lll

-I 0.

-20.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I . 0



150. 1'\. "'- - --... --, .. - "V" -

I

I 00. ·r ..

z ..... z ::> 50.

z <t ' a: 1- 11 lll

o. ....--

f---· ...

--. ..

-· ..

-50.

-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0


Fig. 149 Strain at steam generator inlet nozzle (SE-PC14-l2).

50.

40.

30. z ..... z ::::>

20.

z oC(

a: I 0. 1-lll

0.

-10.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 150 Strain at steam generator outlet nozzle (SE-PC15-l).

7'5.

50.

z

' 25. z ::::>

z 0.

oC(

a: 1-lll

-25.

-50.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0

TIME AFTER RUPTURE (5ECONOSl

Fig. 151 Strain at steam generator outlet nozzle (SE-PClS-2).

95

15.0.

I' ~ 111 ~M11 .d .. Jl-U.l&J I.IIA.tl.1 fl1 11 r IVIJIII'Ir- .,,fl -100. 1 r" r

.tA z

,MJ' l"l .....

z ::J

50.

z < 0:: f.-u·•

o.

~ _____ ... ...... ·····-· .. .... ···- ......

--tM' -····

.. -50.

-0. 1 0. 0 0. 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 . 0


Fig. 152 Stratn at steam generator outlet nozzle (SE-PC15-3).

60.0

50.0

40.0

z ..... z 30.0

z < 0:: 1-

(/l 10.0

-10.0 ~--~----~----~----._--~----~----~----~--~~---L--~

-0. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1. 0


Fig. 153 Strain at steam generator outlet nozzle (SE-PC15-4) ..

96

z

' z :>

z c{

a: 1-Ul

z

' z

:>

z c{

a: 1-Ul

100.

75.

50.

25.

0.

-25.

-0. I 0. 0 0. I 0.2 0.3 0.4 ·0.5 0.6 0.7 0.8 0.9 -

TIME AFTER RUPTURE (5ECON0Sl


150.

100.

50.

o.

-50.

-0. I o". 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

TIME AFTER RUPTURE (5ECONOSl

Fig~ 155 Strain at steam generator outlet nozzle (SE-PC15-6).

97

I. 0

I. 0

150.

100.

z

' z :::>

50.

z oc{

a: 1-Ill

0.

-50.

-o. 1 0 0 0 0 0 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 )•. 0

TIME AFTER RUPTURE (SECONOSJ

Fig. 156 Strain at steam generator outlet n0zzle (SE-PC15-8).

200.

I~U.

z 100.

z :::>

z 50.

oc{

a: I-rJ)

0.

-50.

-o. 1 0 0 0 0 0 1 0 0 2 0 0 3 0 0 4 0 0 5. 0 0 6 0 0 7 0 0 8 0 0 9 1 0 0

TIME AFTER RUPTURE (SECONOSJ

Fig. 157 Strain at steam qenerator outlet nozzle (SE-PC15-9).

98:

z

' z ::::>

z <(

a: 1-Ul

'"·

z

' z ::::>

z <(

a: 1-Ul

150.

100.

50.

0.

-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9



150.

100.

50.

0.

-50.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 159 Strain at st~am generator outlet nozzle (SE-PC15-ll).

~99

I. 0

I. 0

z

' z :::)

z < a: 1-(/)

150.

100.

50.

0.

-50.

-0. I 0. 0 0. I 0 .. 2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 160 Strain at steam generator outlet nozzle (SE-PC15-l2).

I 0.

0.

z ., ·-I 0. z

= -·20. < a: 1-(/1

-3C.

-40.

-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 161 Strain at primary coolant pump. outlet (SE-PC18-l3).

)00

I. 0

I. 0

'-

50.

0.

z ..... z ~

-50.

z < a: ~

lll

-100.

-150.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0


Fig. 162 Strain·at primary coolant pump outlet (SE-PC18-14).

50.

0.

z ..... -50 . z

~ -I 00. < a: ~

lll

-150.

-200.

-0. I

..... ITJ"'M

" ' , ~ "\

• Pt.. .,. I I I

.r. & t; ''IT l .. $d w_. ,.,.. -·~ ,.,. ~ai•L~ '"'PVWV

0. 0 0. I

I,.,.,.. JT I

0.2 0.3 U.4 0.5 0.6 0.7 0.8 0.9


I. 0

Fig. 163 Strain at primary coolant pump outlet (SE-PC18-l5).

101

25.

0.

z ..... z ::> -25.

z < a: I-(/)

-50.

-75.

-0. I 0. 0 0. f 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 164 Strain at primary coolant_pump outlet (SE-PC18-16).

25.

n.

z ..... -25. z ::>

= -50. < a: 1-lll

-75.

-100.

-o. 1 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 165 Stra1n at primary coolant pump outlet (SE-PC18-l7).

102

I. 0

..)

I. 0

z ..... z -:::>

z < a: ..... (/)

z ..... z -:::>

:;;;: -< a: ..... (/)

50.

0.

~ -50.

f--· N

~· . "'' ~ 1---· -· I "J ~T . , ~ I I J -~

-100.

-150.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I .0



50.

25.

0.

~25.

-50 .

-75.

-100.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0



103

z

' z :::>

7:

< a:: 1-(/)

50.

0.

l=W I

-50.

l -tOO. ''H

-150.

-200.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

TIME AFTER RUPTURt !SECONOSl


25.

o.

z ' -25. z :::>

= -50. < a:: 1-(/l

-75.

-100.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9



104

I . 0

I. 0

z

' z ::)

z -t lr ..... (/)

z

50.

0.

-50.

-100.

-150.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9



50.

0.

-50.

= -I 00. -t a: ..... f/l

-150.

-200.

-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9


Fig. 171 Strain at primary coolant pump outlet. (SE-PC18-2'1).

105

I. 0

I. 0

1.

VI. REFERENC.ES

T. K. Samuels, Conformed Copy of LOFT Experiment Operating Specifi

cation, Volume 2, Nonnuclear Test Series Ll Experiment 2, NNE Ll-2,

Revision l (June 1976)_

2. T. K. Samuels, Conformed Copy of LOFT Experiment Operating Specifi

cation, Volume 2, Nonnuclear Test Seri~s Ll Experiment 3 and 3A,

Aerojet Nuclear Cumpany, EOS. Volume 2, NNE U-3 and -3A, Revision 2

(September 1976).

3. H. C. Robinson, Exper·iml:!nt Datu Report for LOFT Nonnuclear

Test Ll-2, TREE-NUREG-1026 (January 1977).

4. G. M. Millar, Experiment Data R!port for LOFT Nonnuclear Test LT-3,

TREE-NUREG-1065 (April 1977).

5. G. M. Millar, Experiment Data Report for LOFT Nonnuclear

Test Ll-3A, TREE-NUREG-1027 (December 1976).

6. H. C. Robinson, LOFT ~ysf.em C:llltl Test DescY'iption (Lns~-of-Cool.af!~·

txper1menLs Using a C:ore Simul_~~o.r), fREE-NURE.G-1019

(November 1976).

7. G. L. Biladeau et al, LOFT Experimental Measurements Unt.:t:!r·tainty

,~.na,ly~is, Aerojet Nuclear Company,

(September 1975).

LTR 141-39,. REG-76-560

II

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6 R. E. Wood,· ID

7 - H. P. Pearson, Supervisor Information Management

8-17 INEL Technical Library

18-37 - Authors

38-266 Special Internal

External Distribution

267'-268 - Saul Levine, Director Office of Nuclear Regulatory Resec.rch, NRC Washington, D. C. 20555

269-315 - Special External

316-619 - Distribuiton under NRC-2, Water Reactor Safety Research Systems Engineering

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