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1核子工程組Engineering Simulator
Licensing Analysis of RPV and BOPBlowdown for the Event of FWLB with RELAP5-3D/K for Lungmen
ABWR Containment Design
Prepared by:Thomas K.S. LiangAffiliated to : Institute of Nuclear Energy Research,
Taiwan
2核子工程組Engineering Simulator
Contents
IntroductionSystem Modeling with RELAP5-3DAssumptionsResultsConclusionsSpecial Issue of LPFL Injection Bypass
3核子工程組Engineering Simulator
Introduction
Conventionally, the limiting break for BWR containment design is the recirculation line break.In the ABWR design, the jet pumps driven by the recirculation loops are replaced by the reactor internal pumps(RIPs).As a result, the limiting break for ABWR containment design shifts to theFeedwater Line Break (FWLB).
4核子工程組Engineering Simulator
Introduction
5核子工程組Engineering Simulator
Introduction
(1) Critical flow at the break ends or the internals, such as FW sparger and venturi;
(2) Flashing of RPV inventory and FW near the break; (3) Run out and coast down of the FW pumps;(4) Steam extractions to FW heaters and FWP turbines; (5) Flashing of saturated water initially stored inside
the FW heater shell sides and MSR drain tanks;(6) Energy release from saturated water and system metal,(7) Cold water transportation from the main condenser to
the break; and (8) ECC injections and associated level variations.
Essential Processes to be calculated
6核子工程組Engineering Simulator
CDSR
FWHTR#3
NPP4 System Simulation Diagram
Steam
Water
Extraction to MSR RHTR #2
Extraction to MSR RHTR #1
GV
NRV
NRV
CV
GV
GV
GV
CV CV
CV
ISOV
LFCV
ISOV
Extraction to HTR#1
Vent from MSR RHTR #2 Drain Tank
Vent from MSR RHTR #1 Drain Tank
Vent from HTR#1
Drain from HTR#6
Drain from MSR RHTR #2 Drain Tank
Drain from MSR RHTR #1 Drain Tank
ORF
ORF
MSLHeader
Extraction to LP FW HTR
Drain from MSRSeparator Drain Tank
ISOV
HP Turbine MSR
RHTR #1Drain Tank
RHTR #2Drain Tank
SeparatorDrain Tank
LP Turbine
ORF
CP
TDFWP
TDFWP
MDFWP
RPV
FromSea
ToSea
MFPT
FWHTR#4
FWHTR#5
FWHTR#6
FWHTR#2
FWHTR#1
NRV
ORF Vent from HTR#2
CV CV
NRV
CV CV CV
Extraction to HTR#2
GV
GV
System Modeling with RELAP5-3D-Modeling Scope-
7核子工程組Engineering Simulator
System Modeling with RELAP5-3D
HPCF
051~059040
061~069060
Act
ive
Cor
e C
hann
el
Byp
ass
Cha
nnel
RCIC
FW
3 RIPsw/o MG Set
3 RIPsw/ MG Set
070
041~049
071071-1
072
036
036-3036-2036-2
036-1034
032
033030 030
028 028
026 026
024 024
022022
020020
010 012014
004
002
FlowRestrictor
100
120
140
160
MSL_A
MSL_B
MSL_C
121
101
141
161
MS Nozzle
102
122
142
162
MS LineSection 1
SRV003A110
SRV004A111
SRV003B130
SRV004B131
SRV003C150
SRV004C151
SRV003D170
SRV004D171
103
123
143
163
MS LineSection 2
SRV005A112
SRV005D172
SRV006D173
SRV006A113
SRV007B134
SRV005B132
SRV006B133
SRV007C154
SRV005C152
SRV006C153
3 RIPsw/ MG Set
1 RIPsw/o MG Set
011
MSL_D
-123 hydraulic nodes-137 junctions-123 heat slabs
Modeling of RPV and Steam Lines
8核子工程組Engineering Simulator
System Modeling with RELAP5-3D
Modeling of Main Steam & Turbine Systems
401MSL
Header
405
403
407
409
411
GV
SP423
From HPTextraciton
To Heater #3
From MSLHeader
CV CV CV
To MSR RHTR#2
extraction
461
MFPT413
extraction
ORF ORF
NRV
To Heater #1
MSR
1st heaterdrain tank1st heaterdrain tank
2nd heaterdrain tank2nd heaterdrain tank
Separatordrain tankSeparatordrain tank
To MSRRHTR#1To MSRRHTR#1
473
NRV
HPTLPT
To CDSR
465
469FromRPV
463
477
481
471
475
479
483
417
415
419
421 4
33
439
443
449
453
455
451
435
441
445
To Heater #1
To Heater #3
To Heater #4
To Heater #5
To Heater #6
467
To Heater #1
To Heater #2
431
437
447
425
427
GV
To CDSR
RHTR#2 RHTR#1501501
502502
503503
504504
505505
506506
507507
508508
511511 512512
513513 516516
519519
514514 517517 520520
522522
532532
533533
534534
535535
515515 518518 521521
536536
540540
541541
542542
543543
544544
545545
546546
547547
550550
551551
552552
553553
554554
555555
556556
557557
561561560560 562562
563563 564564565565
566566 567567
570570
571571574574577577
580580
572572
573573
575575
576576
578578
579579 581581
509509 510510
492
491
493
494
MSIV586586
587587
588588
589589
590590
591591
592592
593593
496
495
497
498
594594
595595
596596
597597
-141 hydraulic nodes
-126 junctions
9核子工程組Engineering Simulator
System Modeling with RELAP5-3D
Modeling of Condensate & Feedwater Systems
TDJ
TDJ
Exhaustfrom MFPT
From Sea
To Sea
TDJ
Drain fromHTR#6
TDJ
Extraction fromLP Turbine#2
Drain from MSRSPRTR Drain Tank
To RPV
Exhaust fromLP Turbine
Vent from HTR#1
ORF
TDJ
ISOV
ISOV
LFCV
ISOVTDV
TDV
TDV
CDSR
601
CP603
HTR#4
TDV
TDFWP647
665
651
673675
TDFWP648
MDFWP649
HTR#5
HTR#2HTR#1
HTR#3
Extraction fromHP Turbine #5
Drain from MSRRHTR #1 Drain Tank
Drain from MSRRHTR #2 Drain Tank
Vent from MSRRHTR #2 Drain Tank
Vent from MSRRHTR #1 Drain Tank
HTR#6
663
Extraction from HPTurbine exhaust
653
ORF
655
Drain toHTR#2
TDJ
TDV
TDJTDJTDJ
Drain fromHTR#2
637
639
Vent from HTR#2
TDJ
Extraction fromLP Turbine#3
TDVDrain fromHTR#3
TDJ
Extraction fromLP Turbine#5
TDVDrain fromHTR#4
TDJ
Extraction fromLP Turbine#6
TDVDrain fromHTR#5
627
629
617
619
607
609
Vent from HTR#3Vent from HTR#4
Vent from HTR#5
Vent from HTR#6
661
625 615 605
CV
Drain toHTR#3TDV
CV
Drain toHTR#4TDV
CV
Drain toHTR#5TDV
CV
Drain toHTR#6TDV
CV
TDV Drain toCDSR
CV
611
657
621
613
623
633
643
641
631
659
667
669
644
645
646
635
TDJ
TDV
Drain fromHTR#1
701
702703
706
707 708
709
710
715716
717
718
719
725726
727
728
729
735
737
738
739
736
745
746
747
748
749
750
753
754
751
752
755
756
761
762
764
765
770
771
773
774
781
782
711
712
713
720
721
722
730
731
732
740
741
742
763
766
767
768
772
775
776
777
671
677
783
786 785 784679
-158 nodes
-151 junctions
-133 slabs
10核子工程組Engineering Simulator
System Modeling with RELAP5-3D
Modeling of FW pump-shaft-turbine module
T D F W P
M F P T4 6 5 4 6 6G V
T o C D S R5 6 25 6 2
56 456 4 5 655 654 6 7
5 6 15 6 1F ro m M S R 9 09 0 19 09 0 1
6 4 49 6 9 019 6 9 01
6 4 79 69 0 29 69 0 2
6 3 57 457 45 F ro m H T R # 3
6 5 17 5 27 5 2
7 6 17 6 17 3 67 3 6
IS O VT o H T R # 2
2 0 5 9 0 92 0 5 9 0 9S H A F T
1000 2000 3000 4000 5000 6000 7000
Capacity [m3/hr]
600
700
800
900
1000
Hea
d [m
]
Turbine Driven Feedwater PumpRELAP5-3DOriginal
11核子工程組Engineering Simulator
System Modeling with RELAP5-3D
Modeling of Inboard & Outboard Breaks
(Outboard Check Valve)(To RPV) (Venturi)
Feedwater Line Header
Feedwater Line A
Feedwater Line B
Inboard BreakNode
(Inboard Check Valve)
Outboard Break Node
Primary Containment Wall
12核子工程組Engineering Simulator
Assumptions
Initial ConditionsParameter Initial Value
(INER)Initial Value(GE)
Reactor Thermal Power [MWt]
4005.0(102 %)
4005.0(102%)
RPV Dome Pressure [MPa]
7.31(102 %)
7.31(102%)
RPV Core Flow [kg/s]
16,107(111.1 %)
16,110(111.1%)
RPV Narrow Range Water Level [cm]
426.0 427.0
Steam and Feedwater Flow [kg/s]
2177.8(102 %)
2174.0(102%)
Feedwater Temperature [°C]
216.9(102 %)
216.9(102%)
13核子工程組Engineering Simulator
Sensitivity Studies
RPV modeling: (1) initial core flow
70 80 90 100 110 120Core Flow [%]
360
370
380
390
400
RPV
Initi
al W
ater
Inve
ntor
y [m
3 ]
RELAP5-3DGE Data (102% of Rated Power)
0 100 200 300 400 500 600 700Time [sec]
-100000
0
100000
200000
300000
400000
500000
Brea
k Fl
ow M
ass
Inte
grat
ion
[kg]
Core Flow85%102%111%
Effect of Core Flow on the Initial RPV Inventory Effect of Initial Core Flow on the Accumulated RPV Blowdown Mass
14核子工程組Engineering Simulator
Assumptions
Plant OperationsExtraction steam continues to enter the feedwater heater and the feedwater
pump turbines until steam inventory is depleted or blocked by the non-return valves designed to protect main turbines;
Non-safety systems and components are assumed to fail in ways that maximum the amount of water mass and energy blowdown;
Feedwater flow to the vessel through the unbroken line continuesintermittently through the event, depending on the feedwater line and RPV pressures.
MSIVs will be fully closed within 3.0-4.5 seconds[3-4], and 3.0 seconds is conservatively assumed for inboard break (RPV and BOP blowdown);
After 30 minutes after break for long term blowdown calculation, HPCF and RCIC injections will be terminated and LPFL injection will be regulated to maintain water level between L-2 and L-8.
15核子工程組Engineering Simulator
Assumptions
Modeling AssumptionsHomogeneous Moody model is applied to calculate blowdown
flow rate;
The effects of internal choking at Venturi of FW system and Spargers inside RPV are considered;
The pump curves of flow run out are used to model the FWPs;
Flashing of water depressurized below its saturation point and the associated effect of flashing on steam supply are considered;
The effect of stored heat from metal and saturated water stored in feedwater heater shell sides on the feedwater heating are considered;
16核子工程組Engineering Simulator
Results
RPV Short-Term Inboard Break
Time [s] Events
0.000 Feedwater line break.
0.310 L-4 and 10 RIPs Runback (L-4 + 0.0s, not apply).
5.000 Reactor scram by drywell high pressure (Assumption).
5.393 L-3, Trip of 4 RIPs without MG set (L-3 + 0.0s).
12.629 L-8, Turbine trip (L-8 + 0.0s, not apply), and Feedwater pump turbine trip (L-8 + 0.0s, not apply).
19.268 MSIVs closure by main steam line low pressure.
26.742 L-2, Trip of 3 RIPs with MG set (L-2 + 0.0s).
31.000 HPCF startup complete (Drywell high pressure + 26.0s).
32.742 Trip of other RIPs with MG set (L-2 + 6.0s).
34.000 RCIC startup complete (Drywell high pressure + 29.0s).
41.000 LPFL startup complete (Drywell high pressure + 36.0s).
Sequence of Events of FWLB Inboard Break
17核子工程組Engineering Simulator
Results
RPV Short-Term Inboard Break
0 100 200 300 400 500 600 700Time [sec]
-3000
0
3000
6000
9000
12000
15000
Brea
k Fl
ow -
RPV
Sid
e [k
g/se
c]
0 100 200 300 400 500 600 700Time [sec]
-500
0
500
1000
1500
2000
2500
3000
Brea
k Fl
ow E
ntha
lpy
- RPV
Sid
e [k
J/kg
]
Break Flow from RPV Side Break Flow Enthalpy from RPV Side
18核子工程組Engineering Simulator
Results
RPV Short-Term Inboard Break
Reactor Water Levels ECC Injection Flows
19核子工程組Engineering Simulator
Results
RPV Short-Term Inboard Break
Pressure Responses before and after MSIV Flows through both the Intact and Broken FW Lines
20核子工程組Engineering Simulator
Results
BOP Short-Term Inboard Break
Feedwater Pump Run out Speed BOP Blowdown Flow Rate
0 100 200 300 400 500 600 700Time [sec]
-1000
0
1000
2000
3000
4000
FWL
Flow
[kg/
s]
Break Line - BOP SideIntact Line
21核子工程組Engineering Simulator
Results
BOP Short-Term Inboard Break
Local voids near the BOP Break End Comparison of the Local Saturation Temperature against the Coming Water Temperature
(Outboard Check Valve)(To RPV) (Venturi)
Feedwater Line Header
Feedwater Line A
Feedwater Line B
Inboard BreakNode
(Inboard Check Valve)
Outboard Break Node
Primary Containment Wall
22核子工程組Engineering Simulator
Results
BOP Short-Term Inboard Break
Extraction Steam Flow from Low Pressure Turbine Feewater Heater Shell Side Pressures
23核子工程組Engineering Simulator
Results
BOP Short-Term Inboard Break
0 100 200 300 400 500 600 700Time [sec]
-200
0
200
400
600
800
1000
1200
Brea
k Fl
ow E
ntha
lpy
- BO
P Si
de [k
J/kg
]
0 30 60 90 120 150 180Time [sec]
0
200000
400000
600000
800000
1000000
Brea
k Fl
ow E
ntha
lpy
[J/k
g]
RELAP5-3D - APKPSAR
BOP Blowdown Enthalpy Comparison BOP Blowdown Enthalpy against PSAR Curve
24核子工程組Engineering Simulator
Results
BOP Short-Term Inboard Break
0 30 60 90 120 150 180Time [sec]
-1000
0
1000
2000
3000
4000
5000
Brea
k Fl
ow [k
g/se
c]
RELAP5-3D - APKPSAR
Comparison of the Blowdown Flow against PSAR Curve
0 30 60 90 120 150 180Time [sec]
-100000000000
0
100000000000
200000000000
300000000000
400000000000
Brea
k Fl
ow E
nerg
y In
tegr
atio
n [J
]
RELAP5-3D - APKPSAR
Comparison of the Accumulated Blowdown Energy against PSAR
25核子工程組Engineering Simulator
Conclusions
The blowdown licensing analysis of FWLB have been successfully analyzed by the advanced RELAP5-3D/K, which include
Inboard & Outboard breakRPV & BOP blodwodnShort term & long term
All essential processes involved can be adequately simulated by RELAP5-3D/K:
(1) critical flow at the break ends or the internals, (2) flashing of RPV inventory and FW near the break,(3) run out and coast down of the FW pumps;(4) steam extractions to FW heaters and FWP turbines;(5) flashing of saturated water initially stored inside systems;(6) energy release from saturated water and system metal,(7) cold water transportation from condenser to the break; and(8) ECC injections and associated level variations.
26核子工程組Engineering Simulator
Conclusions
Through comparisons against the PSAR curves for the inboard break, it was observed that
The revised accumulated blowdown mass can be bounded in the first 180 seconds,The revised accumulated blowdown energy can only be bounded in the first 120 seconds.
27核子工程組Engineering Simulator
Special Issue of LPFL Injection Bypass
What is the LPFL Injection Bypass?A two-phase mixture water column with cold ECC water above might exist in the DCM during a FWLB event.The effective hydraulic head of this mixture water is not enough to bring the DCM water into the core core.Once DCM water level ascends to the FW rings, all the LPFL injection water will be directly driven to the break without entering the core shroud. RIP
LPFLTAF
DCM
28核子工程組Engineering Simulator
Special Issue of LPFL Injection Bypass
0 100 200 300 400 500 600 700Time [sec]
30
40
50
60
70
80
Supp
ress
ion
Pool
Liq
uid
Tem
pera
ture
[o C]
S/P Temperature - GE SupplyS/P Temperature - PDM
29核子工程組Engineering Simulator
Special Issue of LPFL Injection Bypass
RPV Water Level Responses Balance of RPV Boundary Flows
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