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Title: Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks

Abstract

We completed a novel assessment to determine the unquantified and uncredited safety margins (i.e., the difference between the licensing basis and as-loaded calculations) available in as-loaded spent nuclear fuel (SNF) casks. This assessment was performed as part of a broader effort to assess issues and uncertainties related to the continued safety of casks during extended storage and transportability following extended storage periods. Detailed analyses crediting the actual as-loaded cask inventory were performed for each of the casks at three decommissioned pressurized water reactor (PWR) sites to determine their characteristics relative to regulatory safety criteria for criticality, thermal, and shielding performance. These detailed analyses were performed in an automated fashion by employing a comprehensive and integrated data and analysis tool—Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS). Calculated uncredited criticality margins from 0.07 to almost 0.30 Δkeff were observed; calculated decay heat margins ranged from 4 to almost 22 kW (as of 2014); and significant uncredited transportation dose rate margins were also observed. The results demonstrate that, at least for the casks analyzed here, significant uncredited safety margins are available that could potentially be used to compensate for SNF assembly and canister structural performance related uncertainties associatedmore » with long-term storage and subsequent transportation. The results also suggest that these inherent margins associated with how casks are loaded could support future changes in cask licensing to directly or indirectly credit the margins. Work continues to quantify the uncredited safety margins in the SNF casks loaded at other nuclear reactor sites.« less

Authors:
 [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1311216
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 195; Journal Issue: 2; Journal ID: ISSN 0029-5450
Publisher:
American Nuclear Society (ANS)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; spent nuclear fuel; uncredited safety margin; as-loaded casks

Citation Formats

Banerjee, Kaushik, Robb, Kevin R., Radulescu, Georgeta, and Scaglione, John M. Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks. United States: N. p., 2016. Web. doi:10.13182/NT15-112.
Banerjee, Kaushik, Robb, Kevin R., Radulescu, Georgeta, & Scaglione, John M. Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks. United States. doi:10.13182/NT15-112.
Banerjee, Kaushik, Robb, Kevin R., Radulescu, Georgeta, and Scaglione, John M. Wed . "Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks". United States. doi:10.13182/NT15-112. https://www.osti.gov/servlets/purl/1311216.
@article{osti_1311216,
title = {Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks},
author = {Banerjee, Kaushik and Robb, Kevin R. and Radulescu, Georgeta and Scaglione, John M.},
abstractNote = {We completed a novel assessment to determine the unquantified and uncredited safety margins (i.e., the difference between the licensing basis and as-loaded calculations) available in as-loaded spent nuclear fuel (SNF) casks. This assessment was performed as part of a broader effort to assess issues and uncertainties related to the continued safety of casks during extended storage and transportability following extended storage periods. Detailed analyses crediting the actual as-loaded cask inventory were performed for each of the casks at three decommissioned pressurized water reactor (PWR) sites to determine their characteristics relative to regulatory safety criteria for criticality, thermal, and shielding performance. These detailed analyses were performed in an automated fashion by employing a comprehensive and integrated data and analysis tool—Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS). Calculated uncredited criticality margins from 0.07 to almost 0.30 Δkeff were observed; calculated decay heat margins ranged from 4 to almost 22 kW (as of 2014); and significant uncredited transportation dose rate margins were also observed. The results demonstrate that, at least for the casks analyzed here, significant uncredited safety margins are available that could potentially be used to compensate for SNF assembly and canister structural performance related uncertainties associated with long-term storage and subsequent transportation. The results also suggest that these inherent margins associated with how casks are loaded could support future changes in cask licensing to directly or indirectly credit the margins. Work continues to quantify the uncredited safety margins in the SNF casks loaded at other nuclear reactor sites.},
doi = {10.13182/NT15-112},
journal = {Nuclear Technology},
number = 2,
volume = 195,
place = {United States},
year = {2016},
month = {6}
}

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