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.

1. Introduction
2. Methodology and Materials
    2.1 Design Basis Fuels and KRS+ DisposalSystem
    2.2 Design Requirements for Criticality andShielding Calculations
    2.3 Computational Models
3. Results and Discussion
    3.1 Criticality Safety Assessment Results
    3.2 Radiation Shielding Calculation Results
4. Conclusions
REFERENCES

• In-Young Kim(Korea Atomic Energy Research Institute) Corresponding Author
• Dong-Keun Cho(Korea Atomic Energy Research Institute)
• Jongyoul Lee(Korea Atomic Energy Research Institute)
• Heui-Joo Choi(Korea Atomic Energy Research Institute)