On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study
On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study
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快速熔盐堆中轻水堆产生的钚的燃烧——中子物理研究
DOI：
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发表时间：
2015
期刊：
影响因子：
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通讯作者：
D. Litskevich
中科院分区：
文献类型：
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作者：
B. Merk;D. Litskevich
有效燃烧轻水反应堆(LWR)运行中产生的钚有可能显著提高LWR运行的可持续性指数。这项工作比较了不同反应堆配置下钚的燃烧效率--熔盐快堆、混合氧化物(MOX)燃料的轻水堆和钠冷快堆。这些计算是使用HELIOS 2代码执行的。所有结果都是对照中子快速反应(CAPRA)项目所确定的钚燃烧效率进行评估的。在讨论这一结果时，特别考虑到，在成功避免钚积累的情况下，可提高使用轻水再利用的可持续性，否则必须将其提交最终处置。对不可避免的钚生产进行了战略讨论，即焚烧钚的可能性，以避免给子孙后代带来必须控制的负担。
An efficient burning of the plutonium produced during light water reactor (LWR) operation has the potential to significantly improve the sustainability indices of LWR operations. The work offers a comparison of the efficiency of Pu burning in different reactor configurations—a molten salt fast reactor, a LWR with mixed oxide (MOX) fuel, and a sodium cooled fast reactor. The calculations are performed using the HELIOS 2 code. All results are evaluated against the plutonium burning efficiency determined in the Consommation Accrue de Plutonium dans les Reacteurs a Neutrons RApides (CAPRA) project. The results are discussed with special view on the increased sustainability of LWR use in the case of successful avoidance of an accumulation of Pu which otherwise would have to be forwarded to a final disposal. A strategic discussion is given about the unavoidable plutonium production, the possibility to burn the plutonium to avoid a burden for the future generations which would have to be controlled.