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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. Jin a , B. Merrill b , L. V. Boccaccini a 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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  • 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)

  • 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

  • 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.

  • 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

  • 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

  • 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

  • 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

  • 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)

  • 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

  • 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

  • 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.

  • 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