脉冲堆失水事故计算程序的开发和应用

Development and Application of MCRLOCA Code for Pulsed Reactor

由于西安脉冲堆的特点,致使国际上通用的瞬时堆芯裸露模型不能使用。中国核动力研究设计院建立了反映西安脉冲堆失水事故机理和过程的真实堆芯裸露模型,开发了相应的计算机程序,用于分析和评价西安脉冲堆的安全特性。分析结果表明,真实堆芯裸露模型具有广泛的实用性,可用于计算全部侧面破口和底部破口的失水事故。在破口直径相同的条件下,西安脉冲堆侧面破口失水事故后果比底部破口失水事故严重。在目前的设计条件下,即使发生失水事故,西安脉冲堆也能满足安全准则的要求。

Instantaneous Core Uncovered Model(ICUM) common used in the world is not applicable of XiAn pulsed reactor for its characterisitics. Therefore, the True Core Uncovered Model(TCUM) which completely depict the physical process and principle of LOCA for Xi扐n pulsed reactor is established and the relevant LOCA analysis code(MCRLOCA) is developed by the Nuclear Power Institute of China. We comprehensively have analyzed and evaluated the safety of Xi扐n pulsed reactor for LOCA by using the MCRLOCA code. The calculation results of the MCRLOCA code indicates that TCUM is practical and can be used to compute all LOCA with the break on the side and on the bottom. If the diameters of the breaks are identical, the LOCA consequence of the break on the side is more serious than of the break on the bottom. Under present circumstance of XiAn pulsed reactor, safety limit can be met and the reactor is still safe even a LOCA occurs.