摘要
用瞬态有限差分解法计算了氦冷高温气冷堆自然对流问题。分析中采用点松驰方法迭代求解非线性的有限差分方程组，给定边界的温度和计算的几何即可求得速度场和温度场。本文以国际原子能机构（ＩＡＥＡ）关于“高温气冷反应堆系统在事故工况下的热传输和余热导出”问题的合作研究计划（ＣｏｏｒｄｉｎａｔｅｄＲｅｓｅａｒｃｈＰｒｏｇｒａｍ简称ＣＲＰ）的基准试验的部分数据为基础，计算了压力容器内氦气自然对流流场和压力容器外腔室内空气自然对流流场，并与美国Ｂｅｃｈｔｅｌ实验室的计算结果作了比较，结果是合理的。
The pmblem of natural connective flow of high temperature helium cooled reactor is analyzed with a transient finite difference code . The nonlinear finite difference equations are solved itera- tively by a point relaxation technique . Given the temperature of boundaries and the geometry, the fields of the velocity and the temperature can be acquired by the code . According to the data of the benchmark experiment of the IAIEA Coordinated Research Program( CRP ) on Heat Transport and Afterheat Removal for GCRs under Accident Gonditions , helium natural connective flow field in the vessel and air natural connective flow fields in the reactor cavity have been calculated . The calculational results are reasonable in comparison with the analytical results of Bechtel Laboratory Of USA .
出处
《核科学与工程》
CSCD
北大核心
1997年第3期208-214,共7页
Nuclear Science and Engineering
