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作 者:张金玲[1] 郭玉君[1] 苏光辉[1] 秋穗正[1] 贾斗南[1] 喻真烷[1]
机构地区:[1]西安交通大学
出 处:《核科学与工程》1999年第2期97-101,共5页Nuclear Science and Engineering
摘 要:给出了压水堆稳态自然循环的物理与数学模型,并编制了用于分析、计算压水堆稳态自然循环载热能力及与相应参数间关系的程序MISARS。利用MISARS,计算了反应堆各参数对自然循环能力的影响。计算结果符合自然循环规律。本工作对先进压水堆的设计和运行具有重要的意义。The model and the mathematical formulation of the thermohydraulic performance in the steady state natural circulation of nuclear reactor systems was presented in this paper. And the analytical code of the natural circulation, named MISARS, was worked out. Using this code, the effects of the reactor parameters on the capacity of natural circulation were calculated and analysed in detail. The results obtained form the code are in good agreement with the theoretical analysis. The studies in this paper may supply some references for the design and operation of pressurized water reactors.
分 类 号:TL421.103[核科学技术—核技术及应用]
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