Implementation and assessment of improved models and options in TRAC-BF1

被引:5
|
作者
Analytis, GT [1 ]
机构
[1] Paul Scherrer Inst, Lab Thermal Hydraul, CH-5232 Villigen, Switzerland
[2] Paul Scherrer Inst, Lab Thermal Hydraul, CH-5303 Wurenlingen, Switzerland
关键词
D O I
10.1016/S0029-5493(97)00176-3
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A summary of modifications and options introduced in TRAC-BF1 is presented and is shown that the predicting capabilities of the modified version of the code are greatly improved. These changes include the introduction of a different heat transfer package during reflooding, the implementation of a simple single-phase limit procedure for forcing the two phases to acquire the same velocity if one phase disappears, a close assessment of the annular flow interfacial shear correlation, implementation of a simple radiation model which seems to alleviate some numerical-oscillation problems induced by the existing highly complex model. Furthermore, different options were introduced and tested like upwinding some terms of the momentum equations (which seems to solve a number of problems reported in the past), the second upwind scheme for the convective terms of the phasic momentum equations and the implementation and assessment of a completely different annular flow interfacial shear correlation. The modified TRAC-BF1 is assessed against some bottom-flooding separate-effect experiments, a 'benchmark' top flooding simulation as well as against the TLTA test No. 6423. In the process of this task, the different options are assessed and discussed and is shown that the predictions of the modified code are physically sound and close to the measurements, while almost all the predicted variables are free of unphysical spurious oscillations. The modifications introduced solve a number of problems associated with the frozen version of the code and result in a version which can be confidently used for LB-LOCA analyses. (C) 1997 Elsevier Science S.A.
引用
收藏
页码:71 / 97
页数:27
相关论文
共 50 条
  • [1] Implementation and assessment of improved models and options in TRAC-BF1
    Laboratory for Thermal Hydraulics, Paul Scherrer Inst., Wurenlingen V., CH-5232 Villigen PSI, Switzerland
    Nucl Eng Des, 1 (71-97):
  • [2] Assessment of TRAC-BF1 for waterhammer calculations with entrapped air
    Brinckman, KW
    Chaiko, MA
    NUCLEAR TECHNOLOGY, 2001, 133 (01) : 133 - 139
  • [3] Improvements in the decay heat model in the thermalhydraulic code TRAC-BF1
    Soler, A.
    Barrachina, T.
    Miro, R.
    Concejal, A.
    Melara, J.
    Verdu, G.
    INTERNATIONAL JOURNAL OF COMPUTER MATHEMATICS, 2014, 91 (02) : 327 - 335
  • [4] Design and test of an update of TRAC-BF1 for the modelling of supercritical water reactors
    Martinez-Camacho E.
    Morales-Sandoval J.B.
    Gallardo-Villarreal J.M.
    Sánchez-Salazar R.A.
    International Journal of Nuclear Energy Science and Technology, 2020, 14 (03) : 191 - 205
  • [5] Modeling of the interfacial shear in the 3D momentum equations of TRAC-BF1
    Analytis, GT
    ANNALS OF NUCLEAR ENERGY, 2004, 31 (08) : 947 - 960
  • [6] Development, assessment and application of TRAC-BF1/v2001.2 for beyond design basis BWR LOCA transients
    Analytis, GT
    Coddington, P
    ANNALS OF NUCLEAR ENERGY, 2004, 31 (05) : 517 - 540
  • [7] TRAC-BF1/NEM Modeling and results of OECD/NEA BWR core transient benchmarks
    Fu, HY
    Solis-Rodarte, J
    Ivanov, KN
    ANNALS OF NUCLEAR ENERGY, 2000, 27 (12) : 1051 - 1058
  • [8] Analysis of BWR long-term station blackout accident using TRAC-BF1
    Watanabe, Tadashi
    Ishigaki, Masahiro
    Hirano, Masashi
    ANNALS OF NUCLEAR ENERGY, 2012, 49 : 223 - 226
  • [9] TRAC-BF1/NEM stability methodology for BWR core wide and regional stability analysis
    Solís-Rodarte, J
    Ceceñas-Falcón, M
    Ivanov, KN
    Baratta, AJ
    Edwards, RM
    ANNALS OF NUCLEAR ENERGY, 2000, 27 (11) : 985 - 994
  • [10] CONSISTENT GENERATION AND FUNCTIONALIZATION OF ONE-DIMENSIONAL CROSS-SECTIONS FOR TRAC-BF1
    MUNOZCOBO, JL
    VERDU, G
    PEREIRA, C
    ESCRIVA, A
    RODENAS, J
    CASTRILLO, F
    SERRA, J
    NUCLEAR TECHNOLOGY, 1994, 107 (02) : 125 - 137