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Evaluating the BN-800 as a Reactor-Based Option for Plutonium Disposition

机译:评估BN-800作为基于React的Option处置方案

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In 2000, Russia and the United States concluded the Plutonium Management and Disposition Agreement to dispose an amount of 34 tons excess weapon plutonium. Over the last decades, different options to render this plutonium unusable for weapons were discussed. Currently, both states plan to use the plutonium as mixed oxide fuel (MOX) in commercial nuclear reactors. Russia foresees to use it in its sodium cooled fast reactors BN-600 and BN-800, the latter currently still under construction. Both reactors were originally designed as breeder reactors. During the disposition of plutonium, production of fresh plutonium is undesirable. It would take place at least in blankets of depleted or natural uranium. The agreement states that the BN-800 should be operated with a breeding ratio of less than one. We calculate the depletion effects of weapon-grade MOX fuel in the BN-800 for different configurations, with and without breeding blankets. All reactor configurations shift the isotopic composition of spent fuel from core regions to higher Pu isotopes and make the material less weapon-usable, with a Pu-239 content of less than 90 wt%. We analyze the breeding ratios of different configurations and present the resulting spent fuel composition, as well as an estimate of the possible fissile material throughput in the BN-800. All calculations have been carried out using MCMATH, an iterative depletion calculation routine using MCNP and Mathematica. The software has been developed and validated to accommodate many different reactor types and is capable of calculating time-dependent breeding and conversion ratios.
机译:2000年,俄罗斯和美国缔结了《 Management管理和处置协议》,以处置34吨过量武器weapon。在过去的几十年中,讨论了使这种p不能用于武器的各种选择。目前,两国计划在商业核反应堆中将the用作混合氧化物燃料(MOX)。俄罗斯预计将其用于钠冷快堆BN-600和BN-800,后者目前仍在建造中。这两个反应堆最初都设计为增殖反应堆。在处置dis期间,不希望产生新鲜的.。它至少会在贫铀或天然铀的毯子中发生。协议指出,BN-800的繁殖比例应小于1。我们计算了带有和不带有繁殖毯的BN-800中不同配置的武器级MOX燃料的耗尽效应。所有反应堆配置都将乏燃料的同位素组成从核心区域转移到更高的Pu同位素上,并使该材料的武器使用性降低,Pu-239含量小于90 wt%。我们分析了不同配置的繁殖比率,并给出了产生的乏燃料成分,以及对BN-800可能的易裂变材料通过量的估计。所有计算均使用MCMATH进行,MCMATH是使用MCNP和Mathematica进行的迭代耗竭计算程序。该软件已经过开发和验证,可适应许多不同的反应堆类型,并能够计算与时间有关的育种和转化率。

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