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CRITICALITY SAFETY ISSUES IN NUCLEAR DESIGN OF HP-SMTCS SPACE REACTOR

机译:HP-SMTCS空间反应堆核设计中的临界安全问题

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Heat pipe-segmented thermoelectric module converters space reactor power system (HP-SMTCs SRPS) is a promising candidate for space nuclear power system. An examination was taken to discuss the criticality safety of HP-SMTCs reactor core in several accident conditions. In the original nuclear design, the case that reactor core is submerged in wet sand while the voids inside the core are filled with sea water and the BeO reflector are dismantled is defined as the worst status with the highest risk of supercritical. However, recent Monte Carlo transport calculation result shows that reactivity in the case that the core is submerged in water while the voids inside are empty is even higher than those cases with the voids full of sea water, which means that the reactor may encounter high risk of supercritical when some particular accidents occur. Detailed analysis about the neutron energy spectrum and absorption reaction rate is made in order to find out the potential reason of these unexpected results. According to the discussion about the criticality safety issues in some accidents, further evaluations may be necessary for the neutronics design of HP-SMTCs space reactors.
机译:热管分段热电模块转换器空间反应堆动力系统(HP-SMTCs SRPS)是空间核动力系统的有希望的候选者。进行了一次检查,以讨论HP-SMTCs反应堆堆芯在几种事故情况下的临界安全性。在最初的核设计中,将反应堆堆芯浸没在湿沙中,而堆芯内部的空隙中充满海水并拆除BeO反射器的情况被定义为最坏的情况,具有最高的超临界风险。但是,最近的蒙特卡洛输运计算结果表明,堆芯浸入水中而内部空洞为空的情况下的反应性甚至比空洞充满海水的情况下的反应性更高,这意味着反应堆可能会面临很高的风险。当某些特殊事故发生时,它是超临界的。对中子能谱和吸收反应速率进行了详细分析,以找出这些意外结果的潜在原因。根据对某些事故中的临界安全问题的讨论,对于HP-SMTC空间反应堆的中子学设计,可能需要进一步评估。

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