节点文献

PRC-Ⅱ脉冲反应堆事故分析

ACCIDENT ANALYSIS FOR PRC-ⅡREACTOR

  • 推荐 CAJ下载
  • PDF下载
  • 不支持迅雷等下载工具,请取消加速工具后下载。

【作者】 魏永仁; 唐钢; 吴清; 卢毅力; 刘志峰;

【Author】 WEI Yongren, TANG Gang, WU Qing, LUYili, LIU Zhifeng (Nuclear Power Institute of China, Chengdu) (In Chinese)

【机构】 中国核动力研究设计院; 中国核动力研究设计院 成都; 成都; 成都;

【摘要】 <正> 介绍了PRC-Ⅱ脉冲反应堆(中国第二座脉冲反应堆)事故分析中所使用的计算模型、计算机程序、瞬态结果、敏感性研究、设计改进和安全评价。该堆建在人口稠密的城市内,它的安全性格外令人瞩目。为此,对几种假想的事故(提棒事故、弹棒事故和失水事故)进行了详细的计算、分析和评价。针对每种事故工况的机理和过程分别建立了一套复杂的数

【Abstract】 The computer codes, calculation models, transient results, sensitivity research, design improvement, and safety evaluation used in accident analysis for PRO I Reactor (The Second Pulsed Reactor in China) are introduced. PRC- I Reactor is built in big populous city, so the public pay close attention to reactor safety. Consequently, Some hypothetical accidents are analyzed. They include an uncontrolled control rod withdrawal at rated power, a pulse rod ejection at rated power, and loss of coolant accident. Calculation model which completely depict the principle and process for each accident is established and the relevant analysis code is developed. This work also includes comprehensive computing and analyzing transients for each accident of PRC- I Reactor; the influences on the reactor safety of all kind of sensitive parameters ; evaluating the function of engineered safety feature. The measures to alleviate the consequence of accident are suggested and taken in the construction design of PRC- I Reactor. The properties of reactor safety are comprehensively evaluated. A new advanced calculation model (True Core Uncovered Model) of LOCA of PRC- I Reactor and the relevant code (MCRLOCA) are put forward.

  • 【文献出处】 中国核科技报告 ,China Nuclear Science and Technology Report , 编辑部邮箱 ,1997年S1期
  • 【分类号】TL364
  • 【下载频次】34
节点文献中: 

本文链接的文献网络图示:

本文的引文网络