Post on 19-Dec-2015
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
EUROTRANS – DM1
Preliminary Transient Analysis for EFIT with RELAP5 and
RELAP/PARCS Codes
WP5.1 Progress MeetingEmpresarios Agrupados - Madrid, November 13-14, 2007
G. Bandini, P. Meloni, M. Polidori
FPN-FISNUC / Bologna
OUTLINE
RELAP5 Thermal-Hydraulic Model Improvements and EFIT Parameters
List of Transients to be Analyzed by ENEA
Sensitivity Study to Pump Inertia (ULOF)
Definition of Reactor Trip Set-Points
Results of Protected Transients with RELAP5
Analysis of Unprotected Transients with RELAP/PARCS
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
RELAP5 Model Improvements
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
22
112
173
UPPER PLENUMbranch120
110
LOWER PLENUMbranch 100
176 (177/8/9)175
6282
171
branch 160
Jun 106
InnerAverage
151
152153154
111
InnerHot
210211
OuterHot
OuterAverage
pipe281
282/3/4
SGswater side
Pumps113
DHR
Pth
pumpsplenumbranch
121
SGsPb side
SGsPb side
pipe381
382/3/4
annulus181
182/3/4
311310109
CoreMiddle
AverageMiddle
Hot
By pass&
reflector
branch
branchbranch
branch
03 010204050607
07 06 05 04 0203 01
01
01 0101
02
Jun 63Jun 23 Jun 83
Jun 104 Jun 114
01
05
06
01 02
22
112
170
UPPER PLENUMbranch120
110
LOWER PLENUMbranch 100
176 (177/8/9)175
6282
171
branch 160
Jun 106
InnerAverage
152153154
111
InnerHot
210211
OuterHot
OuterAverage
pipe281
282/3/4
SGswater side
113
DHR
Pth
SGsPb side
pipe381
382/3/4
annulus181
182/3/4
311310109
CoreMiddle
AverageMiddle
Hot
By pass&
reflector
branch
branchbranch
branch
03 010204050607
07 06 05 04 0203 01
01 0101
02
Jun 63Jun 23 Jun 83
Jun 104 Jun 114
01
05
06
01 02
0101
0108
108
Tar
get
lo
op
102
161
Jun 105
08
102
161
Jun 105
08
22
112
173
UPPER PLENUMbranch120
110
LOWER PLENUMbranch 100
176 (177/8/9)175
6282
171
branch 160
Jun 106
InnerAverage
151
152153154
111
InnerHot
210211
OuterHot
OuterAverage
pipe281
282/3/4
SGswater side
Pumps113
DHR
Pth
pumpsplenumbranch
121
SGsPb side
SGsPb side
pipe381
382/3/4
annulus181
182/3/4
311310109
CoreMiddle
AverageMiddle
Hot
By pass&
reflector
branch
branchbranch
branch
03 010204050607
07 06 05 04 0203 01
01
01 0101
02
Jun 63Jun 23 Jun 83
Jun 104 Jun 114
01
05
06
01 02
22
112
170
UPPER PLENUMbranch120
110
LOWER PLENUMbranch 100
176 (177/8/9)175
6282
171
branch 160
Jun 106
InnerAverage
152153154
111
InnerHot
210211
OuterHot
OuterAverage
pipe281
282/3/4
SGswater side
113
DHR
Pth
SGsPb side
pipe381
382/3/4
annulus181
182/3/4
311310109
CoreMiddle
AverageMiddle
Hot
By pass&
reflector
branch
branchbranch
branch
03 010204050607
07 06 05 04 0203 01
01 0101
02
Jun 63Jun 23 Jun 83
Jun 104 Jun 114
01
05
06
01 02
0101
01080108
108
Tar
get
lo
op
102
161
Jun 105
08
102
161
Jun 105
08
RELAP5 Nodalization Scheme
Update of steam generator model and secondary side boundary conditions
Primary mechanical pump model added effect of pump inertia in LOF transients
Core pressure drop (grid spacer model added)
Target loop and power removal added
Upper plenum mesh refinement recirculation flows according to SIMMER-III results
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
Primary circuit layout from ANSALDO presentation at the last EUROTRANS - DM4 Technical Review Meeting (March 2007): Reactor core with 3 fuel zones 4 primary pumps, 8 steam generators, 4 secondary loops 4 DHR units (3 out of 4 in operation in transient analysis)
Primary circuit parameters: Reactor thermal power = 395.2 MW Lead mass flowrate = 33230 kg/s Core inlet / outlet temperature = 400 / 480 C Total primary circuit pressure drop = 1.1 bar
(core = 0.45 bar, SG = 0.35 bar, Pump + others = 0.3 bar )
Secondary circuit parameters: Total feedwater flow rate (4 SGs) = 244.4 kg/s, Temperature = 335 C Steam pressure = 140 bar Steam temperature = 452 C (Superheating of 115 C)
EFIT Design and Parameters
Nominal Conditions: RELAP5 Steady-State
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
Maximum temperature
(°C)
Inner zone (Fax = 1.14)
Middle zone (Fax = 1.16)
Outer zone (Fax = 1.17)
Hot FA 1/42
Fr = 1.12
Average FA 41/42
Hot FA 1/66
Fr = 1.13
Average FA 65/66
Hot FA 1/72
Fr = 1.24
Average FA 71/72
Central fuel 1251 1150 1328 1213 1285 1094
Surface fuel 869 818 857 804 816 735
Internal clad 538 523 534 519 535 509
External clad 527 513 524 509 526 501
Lead 494 484 494 483 503 483
Parameter Inner zone
Middle zone
Outer zone
Reflector + by-pass
Target Total
Thermal power (MW) 96 142.3 140.5 5.2 11.2 395.2
Lead mass flow rate (kg/s) 7707 11548 11345 1120 1512 33232
By-pass
outlet
Target
outlet
- -
- -
- -
- -
431 450
List of Transients to be Analyzed by ENEA (1)
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
TRANSIENT TO BE ANALYZED FOR PB-COOLED EFIT DESIGN
Number Transient Description BOC EOCENEA
RELAP5 (X-S) RELAP/PARCS (X-C)
SIMMER
PROTECTED TRANSIENTS
P-1 PLOFTotal loss of forced
circulation in primary system (4 pumps)
x xX-S (reactor trip on
core outlet temp. threshold)
P-1.1 PLOF-1Loss of 1 out of 4
primary pumps (pump rotor seizure)
x xX-S (reactor trip on
core outlet temp. threshold)
P-4 PLOHTotal loss of secondary
loops (4 loops)x x
X-S (reactor trip on core outlet temp.
threshold)
P-4.1 PLOH-1loss of 1 out of 4 secondary loops
x xX-S (reactor trip on
core outlet temp. threshold)
P-5PLOF + PLOH
(station blackout)
Total loss of forced circulation and secondary loops
x xX-S (reactor trip
at 0 s)X (reactor trip at 0 s)
P-10Spurious beam
tripbeam trip for 1,2,3 …..
10 s intervalsx x X-C
P-11 SGTRSteam generator tube rupture (1 to 5 tubes)
xX (reactor trip at 0 s)
List of Transients to be Analyzed by ENEA (2)
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
TRANSIENT TO BE ANALYZED FOR PB-COOLED EFIT DESIGN
Number Transient Description BOC EOCENEA
RELAP5 (X-S) RELAP/PARCS (X-C)
SIMMER
UNPROTECTED TRANSIENTS
U-1 ULOF
Total loss of forced circulation in
primary system (4 pumps)
x x X-C X
U-2 UTOP(?) pcm jump in
reactivity at HFPx x X-C
U-4 DEC ULOHTotal loss of
secondary loops(4 loops)
x x X-C
U-5 DECULOF + ULOH
Total loss of forced circulation and secondary loops
x x X-C
U-11Beam
Overpower to (?)% at HFP
x x X-C
U-12Beam Power
Jump to 100% at HZP
x x X-C
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
Preliminary Analysis of Protected Transients
P-1 – PLOF: Total loss of forced circulation in primary system (4 pumps)
P-1.1 – PLOF-1: Loss of 1 out 4 primary pumps (pump rotor seizure)
P-4 – PLOH: Loss of all secondary loops
P-4.1 – PLOH-1: Loss of 1 out of 4 secondary loops
P-5 – PLOF + PLOH (Station blackout): Total loss of forced circulation and secondary loops and beam trip
REACTOR TRIP: Proton beam switch-off if average core outlet temperature > Threshold set-point (primary pump trip??, actions on secondary side??)
Sensitivity Study to Pump Inertia (ULOF) (1)
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
-20
-10
0
10
20
0 5 10 15 20 25 30
Time (s)
Vel
ocity
(ra
d/s)
Inertia = 20
Inertia = 50
Inertia = 100
Inertia = 200
Pump Velocity
-5000
-2500
0
2500
5000
7500
10000
0 5 10 15 20 25 30
Time (s)
Flo
w r
ate
(kg/
s)
Inertia = 20
Inertia = 50
Inertia = 100
Inertia = 200
Pump Mass Flow Rate Unprotected Loss of Flow accident analysis (4 pumps lost)
Pump inertia varying in the range 20 – 200 kg*m2
Primary pumps stop in few seconds
High pump reverse flow is induced by free level movements
Sensitivity Study to Pump Inertia (ULOF) (2)
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
Inlet Core Mass Flow Rate
Maximum Clad Temperature Core mass flow rate oscillations induced by free level movements
Lowest undershoot for pump inertia in the range 50 – 100 kg*m2
No significant effect of pump inertia on maximum clad temperature peak
Largest value of pump inertia is not favorable
-10000
0
10000
20000
30000
40000
0 5 10 15 20 25 30
Time (s)
Flo
w r
ate
(kg/
s)
Inertia = 20
Inertia = 50
Inertia = 100
Inertia = 200
700
800
900
1000
1100
1200
0 5 10 15 20 25 30
Time (s)
Tem
pera
ture
(K
)
Inertia = 20
Inertia = 50
Inertia = 100
Inertia = 200
Definition of Reactor Trip Set-Points (1)
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
ENTE PERLE NUOVE TECNOLOGIE,L’ENERGIA E L ’AMBIENTE
Empresarios Agrupados – Madrid, November 13-14, 2007, EUROTRANS – DM1 – WP1.5 Progress Meeting
Threshold set-point on measured lead temperature (top assembly, upper plenum average core outlet, pump inlet)
2 2
1 1 2
1 7 3
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 1
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
P u m p s1 1 3
D H R
P t h
p u m p sp l e n u mb r a n c h
1 2 1
S G sP b s i d e
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
2 2
1 1 2
1 7 0
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
1 1 3
D H R
P t h
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
0 10 1
0 10 8
1 0 8
Ta
rg
et
loo
p
1 0 2
1 6 1
J u n 1 0 5
0 8
1 0 2
1 6 1
J u n 1 0 5
0 8
2 2
1 1 2
1 7 3
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 1
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
P u m p s1 1 3
D H R
P t h
p u m p sp l e n u mb r a n c h
1 2 1
S G sP b s i d e
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
2 2
1 1 2
1 7 0
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
1 1 3
D H R
P t h
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
0 10 1
0 10 80 10 8
1 0 8
Ta
rg
et
loo
p
1 0 2
1 6 1
J u n 1 0 5
0 8
1 0 2
1 6 1
J u n 1 0 5
0 8
Upper plenum
Pump
2 2
1 1 2
1 7 3
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 1
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
P u m p s1 1 3
D H R
P t h
p u m p sp l e n u mb r a n c h
1 2 1
S G sP b s i d e
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
2 2
1 1 2
1 7 0
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
1 1 3
D H R
P t h
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
0 10 1
0 10 8
1 0 8
Ta
rg
et
loo
p
1 0 2
1 6 1
J u n 1 0 5
0 8
1 0 2
1 6 1
J u n 1 0 5
0 8
2 2
1 1 2
1 7 3
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 1
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
P u m p s1 1 3
D H R
P t h
p u m p sp l e n u mb r a n c h
1 2 1
S G sP b s i d e
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
2 2
1 1 2
1 7 0
U P P E R P L E N U Mb r a n c h 1 2 0
1 1 0
L O W E R P L E N U Mb r a n c h 1 0 0
1 7 6 ( 1 7 7 / 8 / 9 )1 7 5
6 28 2
1 7 1
b r a n c h 1 6 0
J u n 1 0 6
I n n e rA v e r a g e
1 5 21 5 31 5 4
1 1 1
I n n e rH o t
2 1 02 1 1
O u t e rH o t
O u t e rA v e r a g e
p i p e2 8 1
2 8 2 / 3 / 4
S G sw a t e r s i d e
1 1 3
D H R
P t h
S G sP b s i d e
p i p e3 8 1
3 8 2 / 3 / 4
a n n u l u s1 8 1
1 8 2 / 3 / 4
3 1 13 1 01 0 9
C o r eM i d d l e
A v e r a g eM i d d l e
H o t
B y p a s s&
r e f l e c t o r
b r a n c h
b r a n c hb r a n c h
b r a n c h
0 3 0 10 20 40 50 60 7
0 7 0 6 0 5 0 4 0 20 3 0 1
0 1 0 10 1
0 2
J u n 6 3J u n 2 3 J u n 8 3
J u n 1 0 4 J u n 1 1 4
0 10 5
0 6
0 1 0 2
0 10 1
0 10 80 10 8
1 0 8
Ta
rg
et
loo
p
1 0 2
1 6 1
J u n 1 0 5
0 8
1 0 2
1 6 1
J u n 1 0 5
0 8
Upper plenum
Pump
Clad safety limits for categories DBC II – DBC IV (PDS-XADS):• Tclad max ≤ 823 K with
• time ≤ 600 s at 823 – 873 K
• time ≤ 180 s at 873 – 923 K
ULOH Temperature
Threshold set-point at 773 K on average core outlet temperature limits the maximum clad temperature at 823 K
700
750
800
850
900
950
0 20 40 60 80 100 120
Time (s)
Tem
pera
ture
(K
)
Top assemblyupper plenumpump inletMaximum clad
Threshold set-point at 773 K
Reactor trip
Definition of Reactor Trip Set-Points (2)
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700
750
800
850
900
950
0 10 20 30 40 50 60
Time (s)
Tem
pera
ture
(K
)
Top assembly
upper plenum
pump inlet
Maximum clad
Threshold set-point at 773 KReactor trip
600
700
800
900
1000
1100
1200
0 10 20 30 40 50 60
Time (s)
Tem
pera
ture
(K
)
Top assembly
upper plenum
pump inlet
Maximum clad
Threshold set-point at 773 K
Reactor trip
ULOF Temperature
ULOF (1 Pump) Temperature
The clad safety limit of 823 K is exceeded by 15 K in case of 1 pump trip event and threshold set-point at 773 K on average core outlet temperature
In case of all primary pumps trip the high clad temperature peak cannot be limited by lead temperature threshold on average core outlet temperature
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700
750
800
850
900
950
0 100 200 300 400 500 600
Time (s)
Tem
pera
ture
(K
)
Top assemblyupper plenumpump inletMaximum clad
Threshold set-point at 773 K
Reactor trip
Actions on Primary and Secondary sides are in general needed after automatic proton beam trip to bring the plant in safe conditions and avoid lead overcooling
Actions Following Proton Beam Trip
ULOH (1 Loop) Temperature Primary pump trip
Turbine and feedwater trip
The results of different actions and timing have been evaluated for the initiating event of loss of 1 secondary loop
Beam trip at 120 s when core outlet temperature > 773 K
Actions Following Beam Trip (Short Term)
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Action Primary pump trip Turbine and feedwater trip
1 Never Never
2 At proton beam trip Never
3 30 s after beam trip Never
4 30 s after beam trip 30 s after beam trip
600
650
700
750
800
850
0 100 200 300 400 500
Time (s)
Tem
pera
ture
(K
)
Action 1Action 2Action 3Action 4
600
650
700
750
800
850
0 100 200 300 400 500
Time (s)
Tem
pera
ture
(K
)
Action 1Action 2Action 3Action 4
Maximum Clad TemperatureInlet Core Temperature
Loss of 1 Secondary Loop
Actions Following Beam Trip (Long Term)
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Action Primary pump trip Turbine and feedwater trip
1 Never Never
2 At proton beam trip Never
3 30 s after beam trip Never
4 30 s after beam trip 30 s after beam trip
Maximum Clad TemperatureInlet Core Temperature
Loss of 1 Secondary Loop
600
650
700
750
800
850
0 1000 2000 3000 4000 5000
Time (s)
Tem
pera
ture
(K
)
Action 1Action 2Action 3Action 4
600
650
700
750
800
850
0 1000 2000 3000 4000 5000
Time (s)
Tem
pera
ture
(K
)
Action 1Action 2Action 3Action 4
Preliminary Analysis of Protected Transients
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INITIATING EVENTS: PLOF-1: Loss of 1 out 4 primary pumps
PLOF: Total loss of forced circulation in primary system
PLOH-1: Loss of 1 out of 4 secondary loops
PLOH: Loss of all secondary loops
PLOF + PLOH (Station blackout): Total loss of forced circulation and secondary loops and beam trip
REACTOR TRIP: Proton beam trip if average core outlet temperature > 773 K
Primary pump trip at beam trip
No actions on secondary side
PLOF-1: Loss of 1 Primary Pump (1)
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Primary Pump Mass Flow Rate Inlet Core Mass Flow Rate
Pump 2,3,4 stop(Reactor trip)
Pump 2,3,4 stop(Reactor trip)
Pump 1 lost
Steady-state at 5000 s (primary pump 1 lost with reverse flow)
Pump 2, 3 , 4 stop at reactor trip after about 10 s
PLOF-1: Loss of 1 Primary Pumps (2)
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Lower and Upper Plenum Temperature Maximum Lead Temperature
Reactor trip (T > 773 K)
T max = 839 K(hot channel of outer core)
Reactor trip 10 s after pump 1 stop (T > 773 K)
Maximum lead temperature is 839 K in the hot channel of outer core zone
PLOF-1: Loss of 1 Primary Pumps (3)
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T max = 869 K(hot channel of outer core)
T max = 1620 K(hot channel of middle core)
Maximum Fuel TemperatureMaximum Clad Temperature
Maximum clad temperature exceeds the limit of normal conditions (823 K) but is below the clad safety limit for DBC1- 4 transient conditions (923 K)
Limited fuel temperature increase (below 1620 K)
PLOF-1: Loss of 1 Primary Pumps (4)
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Primary Pump 2, 3, 4 Trip 30 s after Beam Trip
Pump 2,3,4 stop(30 s after reactor trip)
T max = 838 K
Pump 1 lost
Primary Pump Mass Flow Rate Maximum Clad Temperature
Clad temperature peak is limited by delaying primary pump shutdown (30 s) with respect to proton beam switch-off
Beam trip
PLOF: Loss of All Primary Pumps (1)
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Primary Pump Mass Flow Rate Inlet Core Mass Flow Rate
Pump mass flow rate reverses just after stopping (negligible effect of pump inertia)
Initial oscillations of inlet core mass flow rate are due to free level movements and stabilization
PLOF: Loss of All Primary Pumps (2)
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Reactor Trip
Reactor trip about 10 s after pump trip (average lead temp. at core outlet > 773 K)
Large temperature peak due to initial core mass flow rate undershoot
The maximum lead temperature remains well below the boiling point (1476 K)
Lower and Upper Plenum Temperature Maximum Lead Temperature
T max = 995 K(hot channel of outer core)
PLOF: Loss of All Primary Pumps (3)
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T max = 1700 K(hot channel of middle core)
T max = 1080 K(hot channel of inner core)
Maximum Fuel TemperatureMaximum Clad Temperature
Maximum clad temperature exceeds for few seconds the limit of 923 K for DBC1 – 4 transient conditions
The maximum fuel temperature is 1700 K in the hot channel of middle core zone
PLOH-1: Loss of 1 Secondary Loop (1)
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0.E+00
1.E+08
2.E+08
3.E+08
4.E+08
5.E+08
0 100 200 300 400 500
Time (s)
Po
we
r (W
)
Core powerSG power
0
10000
20000
30000
40000
0 100 200 300 400 500
Time (s)
Flo
w r
ate
(kg
/s) mflowj 100080000
600
650
700
750
800
0 100 200 300 400 500
Time (s)
Te
mp
era
ture
(K
)
Lower plenum
Upper plenum
Inlet Core Mass Flow Rate
Upper and Lower Plenum Temp.
Core and SG Power
Reactor trip (T > 773 K)
Pump trip at beam trip
Reactor trip at 120 s (T lead > 773 K, beam and pump trip)
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PLOH-1: Loss of 1 Secondary Loop (2)
Maximum Fuel Temperature
600
800
1000
1200
1400
1600
1800
0 100 200 300 400 500
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
Maximum Clad Temperature
650
700
750
800
850
900
0 100 200 300 400 500
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)Maximum Lead Temperature
650
700
750
800
850
900
0 100 200 300 400 500
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
Lead and clad temperature peaks can be avoided with pump trip delay
Maximum clad temperature peak is within the safety limit for DBC1 – 4 transient conditions
T max = 860 K
T max = 865 K
PLOH: Loss of All Secondary Loops (1)
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Inlet Core Mass Flow RateLower and Upper Plenum Temperature
Reactor trip (proton beam switch-off and pump stop) after 43 s (T lead > 773 K)
Large oscillation of lead mass flow rate at core inlet due to free level movements
Reactor trip (T > 773 K)
Pump trip
PLOH: Loss of All Secondary Loops (2)
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Lower and Upper Plenum TemperatureCore and DHR Power
Maximum DHR performance (3 units) = 20 MW is attained after about 5000 s
Maximum lead temperature stabilizes after about 5000 s at 723 K
PLOH: Loss of All Secondary Loops (3)
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Maximum Vessel TemperatureMaximum Clad Temperature
Maximum clad temperature is 877 K in the hot channel of outer core zone (no peak with delayed pump trip)
Vessel temperature (maximum after about 3000 s) remains below the safety limit (723 K)
T max = 877 K(hot channel of outer core) T max = 722 K
PLOF + PLOH: Station Blackout (1)
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Core and DHR Mass Flow Rate
Core and DHR Inlet/Outlet Temp.
Core and DHR Power
650
680
710
740
770
800
-2000 0 2000 4000 6000 8000 10000
Time (s)
Te
mp
era
ture
(K
)
Core inlet
Core outlet
DHR inlet
DHR outlet
0.0E+00
5.0E+06
1.0E+07
1.5E+07
2.0E+07
2.5E+07
3.0E+07
-2000 0 2000 4000 6000 8000 10000
Time (s)
Po
we
r (W
)
Core power
DHR power
0
1000
2000
3000
4000
5000
-2000 0 2000 4000 6000 8000 10000
Time (s)
Flo
w r
ate
(kg
/s)
Core inlet
DHR inlet
Natural circulation mass flow rate in primary system and DHR power removal confirmed by SIMMER-III 2-D results
DHR mass flow rate in good agreement with ANSALDO specifications at 3600 s (2985 kg/s)
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PLOF + PLOH: Station Blackout (2)
Maximum Fuel Temperature
600
800
1000
1200
1400
1600
1800
-50 0 50 100 150 200 250
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
Maximum Lead Temperature
700
730
760
790
820
850
-50 0 50 100 150 200 250
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
T max = 844 K
Maximum Clad Temperature
700
730
760
790
820
850
-50 0 50 100 150 200 250
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
T max = 848 K
Maximum clad temperature is within the safety limit for DBC1 – 4 transient conditions (time ≤ 600 s at 823 – 873 K)
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PLOF + PLOH: Station Blackout (3)
Maximum Clad Temperature
Maximum Vessel Temperature
Maximum Lead Temperature
700
730
760
790
820
850
-2000 0 2000 4000 6000 8000 10000
Time (s)
Te
mp
era
ture
(K
) ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
700
730
760
790
820
850
-2000 0 2000 4000 6000 8000 10000
Time (s)
Te
mp
era
ture
(K
)
ave (in core)ave (mid core)ave (out core)hot (in core)hot (mid core)hot (out core)
650
670
690
710
730
-2000 0 2000 4000 6000 8000 10000
Time (s)
Te
mp
era
ture
(K
)httemp 100100201
httemp 100100401
httemp 100100601
T limit = 723 K
T max = 715 K
Maximum lead and clad temperatures stabilize around 730 K
Maximum vessel temperature remains below the safety limit