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PROLIFERATION RESISTANCE ASSESSMENTS DURING THE DESIGN PHASE OF A RECYCLING FACILITY AS A MEANS OF REDUCING PROLIFERATION RISKS

机译:回收设施设计阶段的抗扩散性评估,作为降低扩散风险的一种手段

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The sustainability criterion for Gen Ⅳ nuclear energy systems inherently presumes the availability of efficient fuel recycling capabilities. One area for research on advanced fuel recycling concerns safeguards aspects of this type of facilities. Since a recycling facility may be considered as sensitive from a non-proliferation perspective, it is important to address these issues early in the design process, according to the principle of Safeguards By Design. Presented in this paper is a mode of procedure, where assessments of the proliferation resistance (PR) of a recycling facility for fast reactor fuel have been performed so as to identify the weakest barriers to proliferation of nuclear material. Two supplementing established methodologies have been applied; TOPS and PR&PP. The chosen fuel recycling facility belongs to a small Gen Ⅳ lead-cooled fast reactor system that is under study in Sweden. A schematic design of the recycling facility, where actinides are separated using solvent extraction, has been examined. The PR assessment methodologies make it possible to pinpoint areas in which the facility can be improved in order to reduce the risk of diversion. The initial facility design may then be slightly modified and/or safeguards measures may be introduced to reduce the total identified proliferation risk. After each modification of design and/or safeguards implementation, a new PR assessment of the revised system can then be carried out. This way, each modification can be evaluated and new ways to further enhance the proliferation resistance can be identified. This type of iterative procedure may support Safeguards By Design in the planning of new recycling plants and other nuclear facilities.
机译:第四代核能系统的可持续性标准本质上是假定有效的燃料回收能力的可用性。高级燃料回收研究的一个领域涉及此类设施的保障方面。由于从防扩散的角度来看回收设施可能被认为是敏感的,因此根据“按设计保卫措施”的原则,在设计过程中及早解决这些问题很重要。本文介绍的是一种程序模式,其中已经对快堆燃料循环利用设施的扩散阻力(PR)进行了评估,以找出最薄弱的阻碍核材料扩散的障碍。已经应用了两种补充的既定方法; TOPS和PR&PP。所选的燃料回收设施属于瑞典正在研究的小型第四代铅冷却快堆系统。已对回收设施的示意图进行了设计,在回收设施中使用溶剂萃取分离了act系元素。 PR评估方法使查明可以改善设施的区域成为可能,从而降低了转移风险。然后可以对初始设施设计进行一些修改,和/或可以采用保障措施以减少已识别的总扩散风险。在设计和/或保障实施的每次修改之后,可以对修订后的系统进行新的PR评估。这样,可以评估每种修饰,并可以鉴定出进一步增强抗扩散性的新方法。这种类型的迭代过程可能会在新的回收工厂和其他核设施的规划中支持“按计划实施的保障措施”。

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