在反应堆核心和在一个主要的环压力边界裂缝事故以后的一个高温度凉下来气体的反应堆(HTGR ) 的抑制的压力变化决定反应堆的结构的正直和安全。把保存,精力保存和状态基于质量方程,为短暂压力的明确的公式和在压力容器的温度变化被推出,并且为短暂压力的一套微分方程和在抑制的温度变化被开发。数字模拟也被进行在压力容器和抑制调查短暂压力和温度变化。结果证明那精力转变不能由于扩大工作被忽视。在抑制的最大的压力能由于在抑制坐飞机引起的阻塞增加 40% 。在反应堆核心流动段落的短暂压力和温度变化的详细数字模拟也被进行。结果证明对反应堆核心和抑制起作用的压力在可接受的价值下面。
The pressure variances in the reactor core and containment of a High Temperature Gas-cooled Reactor (HTGR) after a primary loop pressure boundary break accident determine the structural integrity and safety of the reactor. Based on mass conservation, energy conservation and state equations, explicit formulae for the transient pressure and temperature variances in the prcssurc vessels were deduced, and a set of differential equations for the transient pressure and temperature vasiances in the containment were developed. Numerical simulation was also conducted to investigate the transient pressure and temperature variances in the pressure vessels and containment. The results show that energy transformation due to expansion work cannot be neglected. The maximum pressure in the containment could increase by 40 percent due to blockage caused by air in the containment. Detailed numerical simulations of the transient pressure and temperature variance in the reactor core flow passages were also conducted. The results show that the pressures acting on the reactor core and containment are below acceptable values.