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Criticality safety analysis of as-loaded spent nuclear fuel casks

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask (both bare fuel and canister-based) system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, as well as the normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by (1) employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory and (2) taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be used to offset uncertainties in the safety basis to account for the effects of system aging during extended dry storage prior to transportation. Additionally, the uncredited criticality margin could also potentially be credited to offset increases in SNF system reactivity that may occur over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific as-loaded criticality margins for 215 loaded casks of SNF stored at eight reactor sites under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 Δkeff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF canisters (for canisterbased systems) in a repository.

Original languageEnglish
Title of host publicationICNC 2015 - International Conference on Nuclear Criticality Safety
PublisherAmerican Nuclear Society
Pages1126-1136
Number of pages11
ISBN (Electronic)9780894487231
StatePublished - 2015
Externally publishedYes
Event2015 International Conference on Nuclear Criticality Safety, ICNC 2015 - Charlotte, United States
Duration: Sep 13 2015Sep 17 2015

Publication series

NameICNC 2015 - International Conference on Nuclear Criticality Safety

Conference

Conference2015 International Conference on Nuclear Criticality Safety, ICNC 2015
Country/TerritoryUnited States
CityCharlotte
Period09/13/1509/17/15

Keywords

  • As-loaded
  • Direct disposal
  • Extended storage
  • Spent nuclear fuel
  • Uncredited criticality margin

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