Nuclear Criticality Calculations for the Wet Handling Facility

The purpose of this calculation is to apply the process described in the TDR-DS0-NU-000001 Rev. 02, Preclosure Criticality Analysis Process Report (Ref. 2.2.25) to aid in establishing design and operational criteria important to criticality safety and to identify potential control parameters and their limits important to the criticality safety of commercial spent nuclear fuel (CSNF) handling operations in the Wet Handling Facility (WHF)
Based on representative assembly designs (Section 1.1.1), facility designs and operational detail (Section 1.1.2), conceptual transport, aging and disposal (TAD) designs (Section 3.1.2), and representative dual-purpose canisters (DPCs) (Section 6.1.4), parameters important to criticality safety are examined and, if needed, parameter limits are determined to ensure subcriticality for normal conditions and potential end states of Category 1 and Category 2 event sequences important to criticality, which are referred to as off-normal conditions throughout this calculation.
While the selected fuel assembly, TAD, and DPC designs are conservatively modeled, they are not necessarily bounding. The trends established in this calculation can, however, be expected to be similar for other fuel assembly, TAD, and DPC designs in regards to reactivity trends, parameters requiring controls, and control limits.
The results presented in Section 6.3 are all based on natural boron with a 10B content of 19.9 atom percent except for the noted results in Section 6.3.5. These include the results presented in Figures 109 through 117.