Containment analysis capability of UNF-ST&DARDS

Georgeta Radulescu; Kaushik Banerjee; Robert A. Lefebvre; L. Paul Miller; John M. Scaglione

doi:10.1080/00295450.2017.1348800

Containment analysis capability of UNF-ST&DARDS

Georgeta Radulescu, Kaushik Banerjee, Robert A. Lefebvre, L. Paul Miller, John M. Scaglione

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

The Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) methodology to perform automated containment analyses for potential transportation packages based on canister loading map information is described, and its capability is illustrated with example results. The allowable leakage rate is calculated with the procedures provided in ANSI N14.5-2014 and NUREG/CR-6487, which were adapted for containment analysis of a transportation package containing fuel assemblies with different nuclear characteristics (e.g., initial enrichment, burnup, and cooling time) and clad integrity (intact or damaged). UNF-ST&DARDS applies different source term calculation methodologies for low-burnup fuel (LBF) (i.e., <45 GWd/tonne U) assemblies and high-burnup fuel (HBF) (i.e., >45 GWd/tonne U) assemblies. The LBF radionuclide activities are based on actual fuel assembly burnup, initial enrichment, and cooling time. Bounding radionuclide activities based on a fuel pellet burnup value of 65 GWd/tonne U and actual fuel assembly cooling time are used for HBF assemblies. The fraction of failed fuel rods and the release fractions for the contributors to releasable source terms recommended in NUREG-1617 are used in the containment analysis regardless of fuel assembly burnup. However, UNF-ST&DARDS supports different parameter values for LBF and HBF assemblies. The containment analysis methodology for as-loaded transportation packages is presented in detail, and the UNF-ST&DARDS containment analysis capability is illustrated with results for simulated transportation packages containing spent nuclear fuel canisters in dry storage at selected sites.

Original language	English
Pages (from-to)	299-309
Number of pages	11
Journal	Nuclear Technology
Volume	199
Issue number	3
DOIs	https://doi.org/10.1080/00295450.2017.1348800
State	Published - Sep 2017

Funding

Development of UNF-ST&DARDS containment analysis capability was accomplished with funding provided by the DOE Office of Nuclear Energy. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the DOE.

Funders	Funder number
DOE Office of Nuclear Energy	DE-AC05-00OR22725
U.S. Department of Energy

Keywords

Containment
Spent Nuclear fuel
UNF-ST&DARDS

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1080/00295450.2017.1348800

Cite this

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title = "Containment analysis capability of UNF-ST&DARDS",

abstract = "The Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) methodology to perform automated containment analyses for potential transportation packages based on canister loading map information is described, and its capability is illustrated with example results. The allowable leakage rate is calculated with the procedures provided in ANSI N14.5-2014 and NUREG/CR-6487, which were adapted for containment analysis of a transportation package containing fuel assemblies with different nuclear characteristics (e.g., initial enrichment, burnup, and cooling time) and clad integrity (intact or damaged). UNF-ST&DARDS applies different source term calculation methodologies for low-burnup fuel (LBF) (i.e., <45 GWd/tonne U) assemblies and high-burnup fuel (HBF) (i.e., >45 GWd/tonne U) assemblies. The LBF radionuclide activities are based on actual fuel assembly burnup, initial enrichment, and cooling time. Bounding radionuclide activities based on a fuel pellet burnup value of 65 GWd/tonne U and actual fuel assembly cooling time are used for HBF assemblies. The fraction of failed fuel rods and the release fractions for the contributors to releasable source terms recommended in NUREG-1617 are used in the containment analysis regardless of fuel assembly burnup. However, UNF-ST&DARDS supports different parameter values for LBF and HBF assemblies. The containment analysis methodology for as-loaded transportation packages is presented in detail, and the UNF-ST&DARDS containment analysis capability is illustrated with results for simulated transportation packages containing spent nuclear fuel canisters in dry storage at selected sites.",

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author = "Georgeta Radulescu and Kaushik Banerjee and Lefebvre, {Robert A.} and Miller, {L. Paul} and Scaglione, {John M.}",

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AU - Scaglione, John M.

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Containment analysis capability of UNF-ST&DARDS

Abstract

Funding

Keywords

UN SDGs

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