改进的KAERI参考处理系统对snf (KRS+)的临界和屏蔽的范围计算

In-Young Kim, D. Cho, Jongyoul Lee, H. Choi
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摘要

本文概述了改进型KAERI SNF参考处置系统(KRS+)的2套KBS-3V型压水堆SNF处置系统和1套nwmo型CANDU SNF处置系统的临界性和辐射屏蔽范围计算结果。结果证实,各处理系统计算的有效乘法系数(keff)均符合设计标准(< 0.95)。在灵敏度研究的基础上,临界边界条件假设了一个充满水的容器,仅含锕系元素的燃料组成,以及数万年的衰变时间。根据初步评估的可能加载区域,确定了一些高富集低燃耗的压水堆SNFs混合加载的必要性。此外,膨润土区域的吸收剂量率远低于设计标准(< 1 Gy·hr-1)。具有不同富集和放电燃耗的整个压水堆snf可以沉积在KRS+系统中,而不存在任何屏蔽问题。考虑到满足屏蔽标准的最小容器厚度,阐明了当前KRS+设计中应用的容器厚度是足够的。综上所述,目前的KRS+设计在核临界性和辐射屏蔽方面是合适的。
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Scoping Calculations on Criticality and Shielding of the Improved KAERI Reference Disposal System for SNFs (KRS+)
In this paper, an overview of the scoping calculation results is provided with respect to criticality and radiation shielding of two KBS-3V type PWR SNF disposal systems and one NWMO-type CANDU SNF disposal system of the improved KAERI reference disposal system for SNFs (KRS+). The results confirmed that the calculated effective multiplication factors (keff) of each disposal system comply with the design criteria (< 0.95). Based on a sensitivity study, the bounding conditions for criticality assumed a flooded container, actinide-only fuel composition, and a decay time of tens of thousands of years. The necessity of mixed loading for some PWR SNFs with high enrichment and low discharge burnup was identified from the evaluated preliminary possible loading area. Furthermore, the absorbed dose rate in the bentonite region was confirmed to be considerably lower than the design criterion (< 1 Gy‧hr-1). Entire PWR SNFs with various enrichment and discharge burnup can be deposited in the KRS+ system without any shielding issues. The container thickness applied to the current KRS+ design was clarified as sufficient considering the minimum thickness of the container to satisfy the shielding criterion. In conclusion, the current KRS+ design is suitable in terms of nuclear criticality and radiation shielding.
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