Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

31
ULTRASONIC INSPECTION OF THE NOZZLES OF CONTROL RODS AND WELD IN REACTOR CORE AREA OF PRESSURE VESSEL OF LOVIISA NPP (VVER440) Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland Bernhard Elsing, Fortum Power and Heat, Loviisa Power Plant, Finland

description

ULTRASONIC INSPECTION OF THE NOZZLES OF CONTROL RODS AND WELD IN REACTOR CORE AREA OF PRESSURE VESSEL OF LOVIISA NPP (VVER440 ). Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland Bernhard Elsing, Fortum Power and Heat, Loviisa Power Plant, Finland. - PowerPoint PPT Presentation

Transcript of Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

Page 1: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

ULTRASONIC INSPECTION OF THE NOZZLES OF CONTROL RODS AND WELD IN REACTOR CORE AREA OF PRESSURE VESSEL OF LOVIISA

NPP (VVER440)

Pentti Kauppinen, Harri Jeskanen, VTT, Finland

Raimo Paussu, Fortum Nuclear Services, Finland

Bernhard Elsing, Fortum Power and Heat, Loviisa Power Plant, Finland

Page 2: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

VTT TECHNICAL RESEARCH CENTRE OF FINLAND

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Control rod penetrations to the closure head

• Target of the inspection

• Structure of the nozzles

• Ultrasonic technique applied

• Performance of measurement

• Results

Page 3: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Upper part of the RPV closure head with control rod housings

Page 4: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Target of the inspection

• The target of the inspection is to assure that water has not penetrated in the narrow gap between the ferritic nozzle penetration tube and the inner corrosion protection tube

• Water can lead to corrosion of the ferritic tube and corrosion products can cause the bulging of inner tube → the operation of control rods is disturbed

• The upper weld inside the penetration nozzle is the susceptible area for leakage

Page 5: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Control rod nozzles: flange between the ferritic penetration tube and austenitic control rod housing

Page 6: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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The structure of the control rod penetration nozzle

Page 7: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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The structure of the control rod penetration nozzle

Page 8: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Principle of the ultrasonic inspection technique

• Test arrangement for laboratory simulations

ferritic plate 15 mm

austenitic plate 3.3 mmWater gap

Transducer 0°

Page 9: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Ultrasonic signals from simulation test and real inspection

• Test with 0.6 mm water gap (above)

• Result from real inspection; water gap 0.75 mm

• Echo on the left is the bottom echo from 15 mm thick nozzle and the echo on the right its multiple

• Measurement is based on the interface echoes (in the gates)

• The width of the gap is calculated based on the distance between the two interface echoes and on the sound velocities in steel and water

Page 10: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Dependence of the interface echo amplitude from the ultrasonic frequency used in inspection

0

5

10

15

20

25

30

0,1 1 10 100

Frequency, MHz

Inte

rfac

e an

d f

law

ref

lect

ion

(d

B)

• At certain frequencies the amplitude drops and the gain setting of the UT-device has to adjusted properly for reliable detection

• Calculation made for 0.2 mm water gap; first drop of amplitude at 3.7 MHz

• 5 MHz transducer was selected for measurements

Page 11: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Performance of inspection: Access to the nozzles

Page 12: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Access to the nozzles

Page 13: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Access to the control rod nozzles

Page 14: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Performance of inspection; access to the nozzles

Page 15: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Measurement signals on the screen of UT-equipment

Page 16: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Opening of a defect detected in the upper weld

Page 17: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Defects on the surface of the corrosion protection tube

Page 18: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Linear crack in the corrosion protection tube

Page 19: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Conclusions from inspections performed

• Based on the measurements performed at Loviisa in 2004-2006 two leaking nozzles were detected

• In both cases the reason for leakage was a manufacturing defect in the upper weld of the corrosion protection tube

• The location of the leakage point could only be detected by helium-test

• The sealing weld at the lower end of the tube has been inspected by eddy current testing and no defects have been found

• The reliability of the inspection is decreased because the measurement of all nozzles can’t be performed along the whole circumference

• In order to have access to the lower part of the nozzle the heat insulation material on the cover should be removed

Page 20: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Inspection of the weld in reactor core area (weld 4)

• The target of the inspection is to assure that the outer surface of the reactor pressure vessel shell is free from defects

• The soundness of outside surface is especially important in possible emergency cooling situation due to the irradiation embrittlement of the reactor pressure vessel material

• Thermal shocks in emergency cooling situation might lead to growth of cracks existing on the outer surface of the shell

Page 21: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Reactor pressure vessel of VVER440

2

3

4

7

6

5

Weld 1

Reactor core area

Page 22: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

VTT TECHNICAL RESEARCH CENTRE OF FINLAND

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Inspection volumes of weld 4 of RPV shell

• Volume A-B-C-D from the outer surface of RPV

• Volume E-F-H-G from the inner surface of RPV

Page 23: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

VTT TECHNICAL RESEARCH CENTRE OF FINLAND

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The transducer packages used for inspection of inner (left) and outer (right) surface of RPV

Page 24: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Telescope mast and the transducers

Page 25: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Telescope mast used in the inspection

Page 26: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Qualification of the technique; detection of 3 implanted defects in a test block. Defect depths 8 , 5 and 3 mm

Page 27: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Qualification of the technique with test block

Page 28: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Inspection technique applied

• For inspection of outer surface area a 70° transmitter-receiver L-wave, 2 MHz probe is used

• The sound beam of the transducer is directed just below the surface in order to detect even very low defects opening to the surface

• For detection of surface opening defects the creeping waves created on the surface

Page 29: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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D- and B-images of indications recorded in the inservice inspections in 2006 (above) and 1999 (below)

Page 30: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Indications on the surface and in the volume of RPV

Page 31: Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

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Conclusions

• The two techniques presented have been developed to complete the basic inservice inspections performed according to ASMEXI

• The feed-back from RPV inspections performed has been good; the reproducibility of results between different years has been excellent

• The opening and repair of control rod nozzles based on the inspection results have verified the conclusions made from UT results

• The inspection of control rod nozzles has certain limitations that should be overcome to improve the overall reliability of the method