The accuracy quantification of thermal-hydraulic code predictions

被引:0
|
作者
Prosek, A [1 ]
Mavko, B [1 ]
机构
[1] Jozef Stefan Inst, Ljubljana 1000, Slovenia
关键词
code accuracy; thermal hydraulic code; SARBM; BETHSY;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Recently, significant attention has been paid to code accuracy issues in predicting the dynamic responses of nuclear reactor systems. Though significant progress has been made, only a few reliable and general tools to quantify code accuracy are available. A new Stochastic Approximation Ratio Based Method (SARBM) was proposed for accuracy quantification. The objective of this study was to investigate and qualify the proposed method. The RELAP5/MOD3.2 thermal-hydraulic code calculations and the BETHSY experimental data were used in the process of qualifying the SARBM with a Fast Fourier Transform Based Method (FFTBM). The obtained results showed that the SARBM was able to satisfactorily predict the accuracy of the calculated transient trends when visually comparing plots and comparing the results with the results obtained by the qualified FFTBM. A new figure of merit for code accuracy, called the accuracy factor (AF), was proposed instead of the stochastic approximation ratio to make the total accuracy calculation with the SARBM more like the FFTBM approach. The accuracy results obtained for the selected BETHSY tests suggest combining the SARBM with the FFTBM for accuracy quantification rather than using it independently. (C) 2003 Journal of Mechanical Engineering. All rights reserved.
引用
收藏
页码:218 / 229
页数:12
相关论文
共 50 条
  • [31] A parallelization approach to the COBRA-TF thermal-hydraulic subchannel code
    Ramos, Enrique
    Abarca, Agustin
    Roman, Jose E.
    Miro, Rafael
    SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
  • [32] Development and validation of thermal-hydraulic and safety analysis code for CARR (TSACC)
    Tian, Wen-Xi
    Qiu, Sui-Zheng
    Su, Guang-Hui
    Jia, Dou-Nan
    Liu, Xing-Min
    Zhang, Jian-Wei
    Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (01): : 40 - 44
  • [33] Development of a thermal-hydraulic analysis code for research reactors with plate fuels
    Lu, Qing
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (04) : 433 - 447
  • [34] Development of Thermal-Hydraulic Analysis Code for Plate Type Fuel Reactor
    Li Lei
    Zhang Zhijian
    2010 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2010,
  • [35] STUDY ON ROD EJECTION ACCIDENT WITH COUPLED NEUTRONIC/THERMAL-HYDRAULIC CODE
    Wang, Xiong
    Li, Qiang
    Wang, Dong
    Ouyang, Yong
    Lu, Xianghui
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 8, 2017,
  • [36] THE ASTEC CODE - AN ALGORITHM FOR SOLVING THERMAL-HYDRAULIC EQUATIONS IN COMPLEX GEOMETRIES
    LONSDALE, RD
    NUCLEAR SCIENCE AND ENGINEERING, 1988, 100 (04) : 385 - 392
  • [37] THERMAL-HYDRAULIC BENCHMARKS
    ESPOSITO, VJ
    MORGAN, CD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 210 - 210
  • [38] VERIFICATION OF CCFL MODEL IN RELAP5 THERMAL-HYDRAULIC CODE
    PARZER, I
    MAVKO, B
    PETELIN, S
    ZEITSCHRIFT FUR ANGEWANDTE MATHEMATIK UND MECHANIK, 1994, 74 (05): : T447 - T451
  • [39] Thermal-hydraulic model of the reactor facility with lead coolant in the ATHLET code
    Chudinova, V. A.
    Nikonov, S. P.
    INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS AND POST-GRADUATES ON NUCLEAR REACTOR PHYSICS, 2018, 1133
  • [40] Uncertainty and sensitivity analyses as a validation tool for BWR bundle thermal-hydraulic predictions
    Hernandez-Solis, Augusto
    Ekberg, Christian
    Demaziere, Christophe
    Jensen, Arvid Odegard
    Bredolt, Ulf
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) : 3697 - 3706