铅基快堆中钋-210迁移的初步研究

Yali Qiu, Q. Zeng, Hongli Chen
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引用次数: 0

摘要

210Po由于其高毒性和挥发性,已成为第四代铅基快堆(LFR)中不可忽视的放射性安全问题。它由冷却剂的中子辐照产生,并发出α射线。当工人在工厂工作时,这可能会造成潜在的内部暴露危害。在反应堆的一次冷却回路中产生的钋由于其挥发性将被释放以覆盖气体。这个过程虽然缓慢,但不容忽视。因此,对M2LFR-1000全堆内的钋迁移和安全室内的钋分布进行了初步分析。根据放射性核素迁移理论,对钋的迁移进行了理论分析,并利用FLUENT软件对钋的分布进行了模拟。模拟了两种情况,一种是正常运行状态,另一种是覆盖气体泄漏事故。初步计算表明,钋在整个空间内分布均匀,仅在某些特殊位置有放射性核素的聚集,在正常运行条件下浓度低于安全水平。分析程序的方法也可用于分析其他放射性核素的分布。
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Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor
210Po has become a non-negligible radioactive safety problem in the fourth generation Lead-based Fast Reactor (LFR) due to its high toxicity and volatility. It will be produced by neutron irradiation of coolant and emits α ray. This may cause potential internal exposure hazards when workers are working in the plant. Polonium produced in the primary coolant circuit of the Reactor will be released to cover gas due to its volatility. This process is slow but not negligible. Therefore, the migration of polonium in the whole reactor and the distribution in the containment room for the M2LFR-1000 was preliminary analyzed. According to the radionuclide migration theory, the migration of polonium was analyzed theoretically, and the distribution of polonium was simulated by FLUENT. Two situations are simulated, one is normal operating condition and the other is leakage accident of covering gas. Preliminary calculation shows that polonium is distributed homogeneously throughout the space with the accumulation of radionuclides only at the certain special place, and the concentrations below safe levels under normal operating conditions. The method of analysis procedure can also be applied to analyze the distribution of other radionuclides.
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