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
  • [21] Effects of dispersed flow interfacial area/shear modeling and node size in the core on TRAC-BF1 rod surface temperature (rst) histories of separate-effect and system calculations (vol 31, pg 255, 2004)
    Analytis, GT
    ANNALS OF NUCLEAR ENERGY, 2004, 31 (06) : 711 - 711
  • [22] ASSESSMENT OF THE TRAC-PF1 STRATIFIED FLOW MODEL
    CAPPIELLO, MW
    LILES, DR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 564 - 565
  • [23] Application of TRAC/BF1-ENTREE-NASCA to OECD NEA/NSC BWR turbine trip benchmark
    Hotta, A
    Zhang, MY
    Shirai, H
    NUCLEAR SCIENCE AND ENGINEERING, 2004, 148 (02) : 208 - 225
  • [24] ASSESSMENT OF THE TRAC-P1A EQUATION-OF-STATE FOR WATER
    SILLING, SA
    SCHROCK, VE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 262 - 263
  • [25] Simulation of boiling water reactor one-pump trip transient by TRAC/BF1-ENTREE
    Hotta, A
    Anegawa, T
    Hara, T
    Ninokata, H
    NUCLEAR TECHNOLOGY, 2003, 142 (03) : 205 - 229
  • [26] TRAC-PF1/MOD1 COMPUTER CODE AND DEVELOPMENTAL ASSESSMENT
    ADDESSIO, FL
    SAHOTA, MS
    LILES, DR
    MAHAFFY, JH
    NUCLEAR SAFETY, 1985, 26 (04): : 438 - 454
  • [27] Biological Principles of Intellectual Motion Control: Models and Implementation Options
    Suyatinov, Sergey
    2019 XXI INTERNATIONAL CONFERENCE COMPLEX SYSTEMS: CONTROL AND MODELING PROBLEMS (CSCMP), 2019, : 187 - 191
  • [28] INDEPENDENT ASSESSMENT OF TRAC-P1A WITH MARVIKEN CRITICAL FLOW TESTS
    ROHATGI, US
    SANBORN, Y
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 304 - 306
  • [29] BWR regional instability analysis by TRAC/BF1-ENTREE - II: Application to ringhals unit-1 stability test
    Hotta, A
    Zhang, M
    Ninokata, H
    NUCLEAR TECHNOLOGY, 2001, 135 (01) : 17 - 38
  • [30] BWR regional instability analysis by TRAC/BF1-ENTREE - I: Application to density-wave oscillation
    Hotta, A
    Honma, M
    Ninokata, J
    Matsui, Y
    NUCLEAR TECHNOLOGY, 2001, 135 (01) : 1 - 16