Fluid-Solid coupling in advanced gas-cooled reactor thermohydraulics

被引:0
|
作者
Uribe, J. [1 ]
Howard, R. [2 ]
Rabbitt, M. [3 ]
机构
[1] Univ Manchester, Sch MACE, Manchester, Lancs, England
[2] EDF R&D, F-78401 Chatou, France
[3] EDF Energy, Nucl Generat, Barnwood GL4 3RS, Glos, England
关键词
WALL;
D O I
10.1615/ICHMT.2012.ProcSevIntSympTurbHeatTransfPal.1350
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The flow inside the under dome section of the Advanced Gas-cooled Reactor has been computed in order to estimate heat transfer coefficient at the dome surface. The fluid simulation is coupled with a heat transfer computation comprising the solid dome and insulation. Three calculations are presented, one LES and two URANS. An elliptic relaxation based method is used in conjunction with an adaptive wall function methodology. This wall treatment allows the model to switch between wall-resolved and wall-model formulations depending on the mesh resolution. The LES results are in better agreement with the frequency response analysis based on plant measurements, whereas the k - epsilon results seem unrealistic. The elliptic relaxation model shows improvement over the standard k - epsilon model but is still far from the LES results.
引用
收藏
页码:1322 / 1333
页数:12
相关论文
共 50 条
  • [31] GAS-COOLED FAST BREEDER REACTOR DESIGNS WITH ADVANCED FUEL AND CLADDING
    FAZZOLARE, R
    NUCLEAR ENGINEERING AND DESIGN, 1977, 40 (01) : 191 - 201
  • [32] Sensitivity analysis of an Advanced Gas-cooled Reactor control rod model
    Scott, M.
    Green, P. L.
    Grant-Wilson, C.
    Bateman, M.
    Worden, K.
    Sims, N. D.
    PROCEEDINGS OF INTERNATIONAL CONFERENCE ON NOISE AND VIBRATION ENGINEERING (ISMA2014) AND INTERNATIONAL CONFERENCE ON UNCERTAINTY IN STRUCTURAL DYNAMICS (USD2014), 2014, : 4587 - 4600
  • [33] MATERIALS FOR PRIMARY CIRCUIT COMPONENTS IN ADVANCED GAS-COOLED REACTOR SYSTEMS
    KIMBALL, OF
    FRANK, RG
    FOX, JE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 200 - 201
  • [34] Sensitivity analysis of an Advanced Gas-cooled Reactor control rod model
    Scott, M.
    Green, P. L.
    O'Driscoll, D.
    Worden, K.
    Sims, N. D.
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 514 - 523
  • [35] GAS-COOLED FAST BREEDER REACTOR
    RICKARD, CL
    BULLETIN D INFORMATIONS SCIENTIFIQUES ET TECHNIQUES, 1971, (162): : 15 - &
  • [36] Radiological characterisation of graphite components in Advanced Gas-cooled Reactor cores
    Tzelepi, A.
    Metcalfe, M. P.
    Dinsdale-Potter, J. H.
    Wilkinson, S.
    Copeland, G.
    JOURNAL OF ENVIRONMENTAL RADIOACTIVITY, 2020, 220
  • [37] STUDY OF DYNAMIC BEHAVIOUR OF SECONDARY CIRCUIT OF GAS-COOLED ADVANCED REACTOR
    LOTH, R
    OFFNER, E
    ATOM & STROM, 1969, 15 (10): : 183 - &
  • [38] Characterising the Radionuclide Fingerprint of an Advanced Gas-Cooled Nuclear Power Reactor
    Goodwin, M. A.
    Petts, A.
    Milbrath, B. D.
    Ringbom, A.
    Chester, D. L.
    Bowyer, T. W.
    Burnett, J. L.
    Friese, J.
    Lidey, L.
    Hayes, J. C.
    Eslinger, P. W.
    Mayer, M.
    Keller, D.
    Sarathi, R.
    Johnson, C.
    Aldener, M.
    Liljegren, S.
    Fritioff, T.
    Kastlander, J.
    Leadbetter, S. J.
    PURE AND APPLIED GEOPHYSICS, 2024,
  • [39] Solid-Core, Gas-Cooled Reactor for Space and Surface Power
    King, JC
    El-Genk, MS
    SPACE TECHNOLOGY AND APPLICATIONS INTERNATIONAL FORUM - STAIF 2006, 2006, 813 : 298 - +
  • [40] FUTURE TECHNOLOGY OF GAS-COOLED REACTOR
    VAUGHAN, RD
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1969, 8 (02): : 134 - &