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Title: CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT

Abstract

Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Al-SNF is subject to corrosion degradation in water storage, and many of the fuel assemblies are ''failed'' or have through-clad damage. A methodology has been developed with technical bases to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. The approach to evaluate the limiting allowable leakage rate, L{sub R}, for a cask with breached Al-SNF for comparison to its test leakage rate could be extended to other nuclear material systems. The approach for containment analysis of Al-SNF follows calculations for commercial spent fuel as provided in NUREG/CR-6487 that adopts ANSI N14.5 as a methodology for containment analysis. The material-specific features and characteristics of damaged Al-SNF (fuel materials, fabrication techniques, microstructure, radionuclide inventory, and vapor corrosion rates) that were derived from literaturemore » sources and/or developed in laboratory testing are applied to generate the four containment source terms that yield four separate cask cavity activity densities; namely, those from fines; gaseous fission product species; volatile fission product species; and fuel assembly crud. The activity values, A{sub 2}, are developed per the guidance of 10CFR71. The analysis is performed parametrically to evaluate maximum number of breached assemblies and exposed fuel area for a proposed shipment in a cask with a test leakage rate.« less

Authors:
; ;
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC
Sponsoring Org.:
USDOE
OSTI Identifier:
881492
Report Number(s):
WSRC-MS-2005-00654
TRN: US0603149
DOE Contract Number:  
DE-AC09-96SR18500
Resource Type:
Conference
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACCIDENTS; CASKS; CONTAINMENT; CORROSION; FABRICATION; FISSION PRODUCTS; FUEL ASSEMBLIES; MICROSTRUCTURE; NUCLEAR FUELS; RADIOISOTOPES; REGULATIONS; RESEARCH REACTORS; SOURCE TERMS; SPENT FUELS; STORAGE; TESTING; TRANSPORT

Citation Formats

Vinson, D. W., Sindelar, R. L., and Iyer, N. C.. CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT. United States: N. p., 2005. Web.
Vinson, D. W., Sindelar, R. L., & Iyer, N. C.. CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT. United States.
Vinson, D. W., Sindelar, R. L., and Iyer, N. C.. Mon . "CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT". United States. https://www.osti.gov/servlets/purl/881492.
@article{osti_881492,
title = {CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT},
author = {Vinson, D. W. and Sindelar, R. L. and Iyer, N. C.},
abstractNote = {Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Al-SNF is subject to corrosion degradation in water storage, and many of the fuel assemblies are ''failed'' or have through-clad damage. A methodology has been developed with technical bases to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. The approach to evaluate the limiting allowable leakage rate, L{sub R}, for a cask with breached Al-SNF for comparison to its test leakage rate could be extended to other nuclear material systems. The approach for containment analysis of Al-SNF follows calculations for commercial spent fuel as provided in NUREG/CR-6487 that adopts ANSI N14.5 as a methodology for containment analysis. The material-specific features and characteristics of damaged Al-SNF (fuel materials, fabrication techniques, microstructure, radionuclide inventory, and vapor corrosion rates) that were derived from literature sources and/or developed in laboratory testing are applied to generate the four containment source terms that yield four separate cask cavity activity densities; namely, those from fines; gaseous fission product species; volatile fission product species; and fuel assembly crud. The activity values, A{sub 2}, are developed per the guidance of 10CFR71. The analysis is performed parametrically to evaluate maximum number of breached assemblies and exposed fuel area for a proposed shipment in a cask with a test leakage rate.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Nov 07 00:00:00 EST 2005},
month = {Mon Nov 07 00:00:00 EST 2005}
}

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