DISPOSABILITY OF LOADED U.S. DUAL-PURPOSE CANISTERS FROM A CRITICALITY STANDPOINT
This paper assesses the feasibility of direct disposal of loaded dual-purpose canisters (DPCs) from a criticality standpoint by evaluating attributes that could be credited to justify that the DPCs remain subcritical over a repository performance period. This study investigates the uncredited criticality margin associated with actual fuel loading compared with the regulatory licensing design basis limits and evaluates the percentage of DPCs that remain subcritical solely based on the uncredited criticality margin.
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slides - DPC Direct Disposal Feasibility Evaluation: Concept Development and Analysis
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
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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)
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YMP Preliminary Wet Handling Facility Throughput Study
This study describes the development of a preliminary throughput estimate for a Wet Handling Facility (WHF)/ used fuel repackaging factility. This study estimates the throughput for the WHF License Application design for a repository at Yucca Mountain as of September 2007. This design freeze allowed for the development of the throughput study without having to accommodate for minor updates to the facility design and documentation leading up to the License Application.
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The Potential of Using Commercial Dual Purpose Canisters for Direct Disposal
This report evaluates the potential for directly disposing of licensed commercial Dual Purpose
Canisters (DPCs) inside waste package overpacks without reopening. The evaluation considers
the principal features of the DPC designs that have been licensed by the Nuclear Regulatory
Commission (NRC) as these relate to thedesigns of waste packages and as they relate to
disposability in a repository in unsaturated volcanic tuff. Where DPC features appear to compromise future disposability in an unsaturated tuff (e.g., Yucca Mountain) repository
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