Development of TSAC1.0 and application to reactivity insertion accident of CARR

Ronghua Chen, G. H. Su, Wenxi Tian*, Suizheng Qiu, Dounan Jia

*この研究の対応する著者

研究成果: Article査読

抄録

In this study, we have developed a thermo-hydraulic and safety analysis code named TSAC1.0 with Visual Fortran 6.5 to analyze the thermal-hydraulic characteristics of the China advanced research reactor (CARR) under reactivity insertion accident (RIA) which was induced by unexpected control rod withdrawal in full power condition. The neutron kinetic model depended on the point kinetics with six groups of delayed neutrons including reactivity feedback effects and it was adopted for the solution of reactor power. Furthermore, a new simple and convenient model was adopted for the solution of the transient behaviors of main pump instead of the complicated four-quadrant model. Visual input, real-time processing and dynamic visualization output were achieved using Microsoft Visual Studio.NET 2003 to make the application of TSAC1.0 much more convenient in the engineering. The simulated results of TSAC1.0 were found to be in reasonable agreement with those of RELAP5/MOD3 and showed that the parameters, including the peak coolant temperature, the peak heat structure temperature, and MDNBR, were in the acceptable range of design safety limit under RIA.

本文言語English
ページ(範囲)1-9
ページ数9
ジャーナルProgress in Nuclear Energy
53
1
DOI
出版ステータスPublished - 2011 1

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学
  • 廃棄物管理と処理
  • 安全性、リスク、信頼性、品質管理

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