ex-vessel loca for the european hcpb tbm system using the … · 2020. 1. 9. · ex-vessel loca for...
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KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association
Institute of Neutron Physics and Reactor Technology (INR)
www.kit.edu
Ex-vessel LOCA for the European HCPB TBM system using the pedigreed MELCOR182 for fusion
X. Jina, B. Merrillb, L. V. Boccaccinia
The 4th Meeting of the “European MELCOR User Group”
Cologne , Germany
April 16-17, 2012
a Karlsruhe Institute of Technology (KIT)b Idaho National Laboratory (INL)
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Institute of Neutron Physics and Reactor Technology (INR)
2 4th EMUG X. Jin
Outline
Pedigreed MELCOR182 for fusion
HCPB TBM and HCS
Ex-vessel LOCA
Accidental sequence
MELCOR model for helium blow-down
MELCOR 3D-model for ½ BU
MELCOR results & open issues
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Institute of Neutron Physics and Reactor Technology (INR)
3 4th EMUG X. Jin
Pedigreed MELCOR182 for fusion
* Merrill B.J., Modifications to the MELCOR code for application in fusion accident analyses, Fusion Engineering and Design 51-52, 2000.
The version is modified by INL for ITER purposes*:
chemical oxidation reactions of steam with Be, C and W,
extension of water properties below its triple point temperature for Loss Of Coolant Accidents (LOCAs) into cryostats,
the cryogenic He or air as the primary fluid,
convective boiling,
HTO transport,
enclosure radiant heat transfer.
In 2010 input deck limited to 9999 lines were extended, but the limitation for CV, FL, CF and TF (999) is not changed.
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Institute of Neutron Physics and Reactor Technology (INR)
4 4th EMUG X. Jin
HCPB TBM and the combined HCSVertical TBM box
Breeder Unit (BU)
HCS and results at steady state (RELAP5-3D)
Ex-vessel LOCA is assumed at the steady stateHCPB: Helium Cooled Pebble Bed FW: First Wall TBM: Test Blanket Module BU: Breeder UnitHCS: He Cooling System MF: ManifoldPCS: Pressure Control System MX: Mixer
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Institute of Neutron Physics and Reactor Technology (INR)
5 4th EMUG X. Jin
Accidental sequence
HCPB TBM & HCS(Steady state)
Ex-vessel LOCAinside port cell
Helium blow-down(HCPB TBM & HCS)
Active plasma shutdown
fast plasma shutdown
(3s)
yes
yes Be-steam reaction(TBM box)
Failures of ITER FW & TBM FW
yes
no
T behavior
T behavior & H2 production
RELAP5-3D
MELCOR
MELCOR
ANSYS
Plasma disruption(1s)
ANSYS 3D-model of the TBM with ¼ BU
CTmolKJHBeOOHBe 300,/37022 ANSYS-temperatures after the plasma disruption are MELCOR initial temperatures.
470490510530550570590610630650670690710730750770
0 25 50 75 100
125
150
175
200
225
250
275
300
325
350
time (s)
Tem
pera
ture
(°C
)
FW
ANSYS calculation
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Institute of Neutron Physics and Reactor Technology (INR)
6 4th EMUG X. Jin
Helium blow-down inside port cell
MELCOR nodalization for the HCS and HCPB TBM
Location of the port cell & HCPB TBM *
* Boccaccini L.V. et al., Present status of the conceptual design of the EU test blanket systems, Fusion Engineering and Design 86(2011) 478-483.
CVCS: Chemical and Volume Control Systems
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Institute of Neutron Physics and Reactor Technology (INR)
7 4th EMUG X. Jin
Pressure behavior inside port cell & pressure drop of the system
9.950E+04
1.112E+05
1.229E+05
1.346E+05
1.463E+05
1.580E+05
1.697E+05
1.814E+05
1.931E+05
2.048E+05
2.165E+05
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20
time (s)
Pre
ssur
e (P
a)
0%
10%
20%
30%
40%
50%
60%
70%
80%
90%
100%
port cell, with VDSport cell, no VDSITER limitpressure drop (%)
MELCOR nodalization for the VDS
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Institute of Neutron Physics and Reactor Technology (INR)
8 4th EMUG X. Jin
Beryllium–steam reaction in the long term
VVPSS: Vacuum Vessel Pressure Suppression System
MELCOR modelling for failures of ITER FW & TBM FW
(1.57E-3m²) (2.7E-3m²)
(1.2963E-3 m²)
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Institute of Neutron Physics and Reactor Technology (INR)
9 4th EMUG X. Jin
MELCOR 3D-model for ½ BU
190
402
29.5 5
61
22
EUROFER
BERYLLIUM
Li4SiO4
R45R25
151
CVjiki=5
152 153 154 155 156
251 252
351 353 354 355 356
FW
25
BU
ada
pter
335
HG18010050
25
rad (k)
pol (j)
cap
VG
HG
206.5
6
113
CVjikk=3
123 133 143 153 163 173 183 193
213 293
313 323 333 343 353 363 373 383 393
194.5
tor (i)
pol (j) 12 24 40 42.5
• modeling for 1 pebble d1peb = 1 mm, HSMULT = Npeb.
• thermal conduction between adjacent cells by modeling the heat conducted from one cell to be received by a HS in the adjacent cell in the given direction.
• internal power source: decay heat as table function ~ time.
• radiation: gray-gas-a, emissivity 0.65.
Cells: 3x9x6 = 162
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Institute of Neutron Physics and Reactor Technology (INR)
10 4th EMUG X. Jin
VV135°C, 1 Pa
1090 m³CV401
FL405
Water source(FW/BLK)
135°C, 3 MPa,140m³, CV403
FL403
VVPSS
HCPB TBM HCS
VDS
FW 1 6 pipesCV720
Be pebCV351
VVp & T
CV401½ BU
FL401
FL402
p & T of the VV ~ time(ICVAT=-2)
Failure of TBM FW to the beryllium pebble bed
Failures of ITER FW & TBM FW to the VV
(1.57E-3m²)
(2.7E-3m²)
(1.2963E-3 m² / 2)
MELCOR simulations
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Institute of Neutron Physics and Reactor Technology (INR)
11 4th EMUG X. Jin
MELCOR results in the long term
Temperature behavior and H2 production
t = 6.335626E+02 DT(CVH) = 1.241800E-05CPU = 1.469860E+07 = 170 days
0.0E+00
2.0E+04
4.0E+04
6.0E+04
8.0E+04
1.0E+05
1.2E+05
1.4E+05
1.6E+050
500
1000
1500
2000
2500
3000
3500
4000
4500
5000
time (s)
Pre
ssur
e (P
a)
30
50
70
90
110
130
150
170
190
Tem
pera
ture
(°C
)
total pp_steamT
Pressure and temperature behavior in the VV
0.0E+00
5.0E-06
1.0E-05
1.5E-05
2.0E-05
2.5E-05
3.0E-05
0 40 80 120
160
200
240
280
320
360
400
440
480
520
560
600
640
680
time (s)
Mas
s (K
g)
440
465
490
515
540
565
590
Tem
pera
ture
(°C
)
CVH-TOT-M.4CVH-TVAP_351
H2 -results for the first 400s are shown in [1] Jin X., Merrill B.J., Boccaccini L.V., Preliminary safety analysis of ex- vessel LOCA for the European HCPB TBM system, Fusion Engineering and Design, in press.
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Institute of Neutron Physics and Reactor Technology (INR)
12 4th EMUG X. Jin
Open issues
Helium is treated as noncondensible gas.
CVH-TOT-M.4 cannot show the total H2 production of the system because p&T of the VV are specialized as a function of time.
Round-off error due to the single precision of the version 1.8.2
limitation for CV, FL, CF and TF (999).
Updated MELCOR version for fusion is needed !
Foliennummer 1OutlinePedigreed MELCOR182 for fusionHCPB TBM and the combined HCSAccidental sequenceHelium blow-down inside port cell Foliennummer 7Beryllium–steam reaction in the long term MELCOR 3D-model for ½ BUMELCOR simulationsMELCOR results in the long termOpen issues