VALIDATION OF THE TEXSAN THERMAL-HYDRAULIC ANALYSIS PROGRAM

被引:0
|
作者
BURNS, SP
KLEIN, DE
机构
[1] Univ of Texas at Austin, Austin, TX
关键词
NUMERICAL; VALIDATION; THERMAL HYDRAULICS;
D O I
10.13182/NT93-A34879
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
The TEXSAN thermal-hydraulic analysis program was developed to simulate buoyancy-driven fluid flow and heat transfer in spent-fuel and high-level nuclear waste (HLW) shipping applications. The TEXSAN design has sufficient flexibility to conduct full cask analysis as well as small-scale heat and mass transfer simulations on a rod-to-rod basis within an individual fuel assembly. As part of the TEXSAN soft ware quality assurance program, the software has been subjected to a series of test cases intended to validate its capabilities. The validation tests include many physical phenomena that arise in spent-fuel and HLW shipping applications. Some of the principal results of the TEXSAN validation tests are described, and they are compared with solutions available in the open literature. The TEXSAN validation effort has shown that the TEXSAN program is stable and consistent under a range of operating conditions and provides accuracy comparable with other heat transfer programs and evaluation techniques. The modeling capabilities and the interactive user interface employed by the TEXSAN program should make it a useful tool in HLW transportation analysis.
引用
收藏
页码:157 / 163
页数:7
相关论文
共 50 条
  • [1] Experimental validation of the thermal-hydraulic code SACATRI
    Merroun, O.
    Al Mers, A.
    Veloso, M. A.
    El Bardouni, T.
    El Bakkari, B.
    Chakir, E.
    NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (12) : 2875 - 2884
  • [2] 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
  • [3] THE USNRC THERMAL-HYDRAULIC RESEARCH-PROGRAM
    SHOTKIN, LM
    BESSETTE, D
    NUCLEAR ENGINEERING AND DESIGN, 1993, 139 (01) : 141 - 147
  • [4] Measurements for verification and validation of thermal-hydraulic computer code used for thermal-hydraulic analysis of VVER440 typical fuel assembly
    Ezsol, Gyorgy
    Hutli, Ezddin
    Valer, Gottlasz
    Gabor, Zsiros
    MEASUREMENT, 2021, 171
  • [5] CONTRIBUTION TO THERMAL-HYDRAULIC STABILITY ANALYSIS
    GROSS, RJ
    SEE, FT
    MECHANICAL ENGINEERING, 1974, 96 (04) : 81 - 81
  • [6] Thermal-Hydraulic analysis of hydrodynamic coupling
    Wei, Cai
    Lidan, Fan
    Wenxing, Ma
    Advances in Information Sciences and Service Sciences, 2012, 4 (11): : 393 - 399
  • [7] DEBRIS THERMAL-HYDRAULIC ANALYSIS IN SCDAP
    HSIEH, TS
    ALLISON, CM
    HOWE, TM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 803 - 804
  • [8] ATLAS program for advanced thermal-hydraulic safety research
    Song, Chul-Hwa
    Choi, Ki-Yong
    Kang, Kyoung-Ho
    NUCLEAR ENGINEERING AND DESIGN, 2015, 294 : 242 - 261
  • [9] Validation of coupled thermal-hydraulic and neutronics codes for safety analysis by international cooperations
    Ivanov, Kostadin
    Sartori, Enrico
    Royer, E.
    Langenbuch, S.
    Velkov, K.
    NUCLEAR TECHNOLOGY, 2007, 157 (02) : 177 - 195
  • [10] Rod Bundle Heat Transfer Thermal-Hydraulic Program
    Bajorek, Stephen M.
    Cheung, Fan-Bill
    NUCLEAR TECHNOLOGY, 2019, 205 (1-2) : 307 - 327