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
  • [21] Thermal-Hydraulic Analysis of the DEMO CS Coil
    Dembkowska, Aleksandra
    Lewandowska, Monika
    Sarasola, Xabier
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2018, 28 (04)
  • [22] TRANSIENT THERMAL-HYDRAULIC ANALYSIS FOR REACTOR CORES
    YAO, LS
    CATTON, I
    GAZLEY, C
    NUCLEAR ENGINEERING AND DESIGN, 1977, 44 (01) : 43 - 51
  • [23] Thermal-hydraulic analysis of GFR demonstrator - Allegro
    Siwiec, Arkadiusz
    Spirzewski, Michal
    27TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2018), 2018,
  • [24] THERMAL-HYDRAULIC BENCHMARKS
    ESPOSITO, VJ
    MORGAN, CD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 210 - 210
  • [25] Thermal-hydraulic analysis of SWAMUP test facility
    Wang, Zi-Di
    Cao, Zhen
    Liu, Xiao-Jing
    Cheng, Xu
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2015, 49 (07): : 1191 - 1199
  • [26] THERMAL-HYDRAULIC ANALYSIS OF THE BYPASS FLOW IN BWRS
    JACKSON, JW
    TODREAS, NE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 771 - 772
  • [27] REFINED NUMERICAL MODELING IN THERMAL-HYDRAULIC ANALYSIS
    VIOLLET, PL
    GRAND, D
    CHABARD, JP
    MAGNAUD, JP
    HOUILLE BLANCHE-REVUE INTERNATIONALE DE L EAU, 1995, 50 (01): : 34 - 53
  • [28] Development of a thermal-hydraulic analysis code for CARR
    Tian, WX
    Qiu, SZ
    Guo, Y
    Su, GH
    Jia, DN
    ANNALS OF NUCLEAR ENERGY, 2005, 32 (03) : 261 - 279
  • [29] Treatment of the thermal-hydraulic uncertainties in the pressurized thermal shock analysis
    Jang, Changheui
    NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (02) : 143 - 152
  • [30] Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors
    Hu, Siqin
    Zhou, Chong
    Zhu, Guifeng
    Zou, Yang
    Yu, Xiaohan
    Xue, Shuaiyu
    He Jishu/Nuclear Techniques, 2024, 47 (09):