压水反应堆稳态热工设计程序开发
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摘要
核反应堆稳态热工设计是反应堆堆芯设计的基础,是确保反应堆安全稳定运行的重要保障。为探索反应堆稳态热工设计的设计过程,验证所选取的计算模型和计算公式是否满足要求,本文在给定设计准则和已知参考堆部分参数的条件下,采取开发一个压水反应堆稳态热工设计程序的方式,计算出多种工况下堆芯的运行参数并开展分析,以进行相关验证。经过对计算结果进行分析,表明该程序所计算出的各参数基本符合实际情况,并满足热工设计准则,说明该程序的计算过程基本上是正确的,可以用来做反应堆稳态热工设计。同时,也证明了本文采用的计算模型、设计准则、计算过程公式、程序设计流程等是可行的,可为其他反应堆稳态热工设计及程序开发提供参考。
The steady-state thermal engineering design of nuclear reactors is the basis of reactor core design and is an important guarantee for ensuring the safe and stable operation of reactors. In order to explore the design process of the reactor steady-state thermal engineering design and verify whether the selected calculation model and calculation formula meet the requirements, this paper calculates and analyzes the core operating parameters under various operating conditions and carries out relevant verification, by developing a steady-state thermal design program for the pressurized water reactor, with given design criteria and known partial parameters of the reference reactor. After analyzing the calculation results, it shows that the parameters calculated by the program basically conform to the actual conditions and meet the thermal engineering design criteria, indicating that the calculation process of the program isbasically correct and can be used to make the reactor steady-state thermal design. At the same time, it also proves that the calculation model, design criteria, calculation process formula and program design flow adopted in this paper are feasible, and can provide reference for other steady-state thermal design and program development.
The steady-state thermal engineering design of nuclear reactors is the basis of reactor core design and is an important guarantee for ensuring the safe and stable operation of reactors. In order to explore the design process of the reactor steady-state thermal engineering design and verify whether the selected calculation model and calculation formula meet the requirements, this paper calculates and analyzes the core operating parameters under various operating conditions and carries out relevant verification, by developing a steady-state thermal design program for the pressurized water reactor, with given design criteria and known partial parameters of the reference reactor. After analyzing the calculation results, it shows that the parameters calculated by the program basically conform to the actual conditions and meet the thermal engineering design criteria, indicating that the calculation process of the program isbasically correct and can be used to make the reactor steady-state thermal design. At the same time, it also proves that the calculation model, design criteria, calculation process formula and program design flow adopted in this paper are feasible, and can provide reference for other steady-state thermal design and program development.
引文
[1]陈叔平等译.沸腾传热和两相流译文集[M].北京:原子能出版社,1981.
[2]E.史密特,U.格里古尔编,赵兆颐译.国际单位制的水和水蒸气性质[M].北京:水利电力出版社,1983:173.
[3]任功祖.动力反应堆热工水力分析[M].北京:原子能出版社,1982.
[4]彭木彰,赵兆颐.水在管内湍流放热公式的简化[R].清华大学科学报告,1980.
[2]E.史密特,U.格里古尔编,赵兆颐译.国际单位制的水和水蒸气性质[M].北京:水利电力出版社,1983:173.
[3]任功祖.动力反应堆热工水力分析[M].北京:原子能出版社,1982.
[4]彭木彰,赵兆颐.水在管内湍流放热公式的简化[R].清华大学科学报告,1980.