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Title: TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events

Abstract

The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (10 CFR), Title 10, Part 71 [1]. Both the International Atomic Energy Agency regulations for transporting radioactive materials [2, paragraph 727], and 10 CFR 71.73 require casks to be evaluated for hypothetical accident conditions, which includes a 9-meter (m) (30-ft) drop-impact event onto a flat, essentially unyielding, horizontal surface, in the most damaging orientation. This paper examines the behavior of one of the NRC certified transportation casks, the TN-68 [3], for drop-impact events. The specific area examined is the behavior of the bolted connections in the cask body and the closure lid, which are significantly loaded during the hypothetical drop-impact event. Analytical work to evaluate the NRC-certified TN-68 spent fuel transport cask [3] for a 9-m (30-ft) drop-impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS® [4] and LS DYNA™ [5] finite-element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9-m (30-ft) free-drop hypothetical accident conditions, as specified in 10 CFRmore » 71.73. Evaluation of the cask for puncture, caused by a free drop through a distance of 1-m (40-in.) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71.73, was not included in the current work, and will have to be addressed in the future. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the lid surfaces may occur under some conditions, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
951568
Report Number(s):
PNNL-SA-54285
401001050; TRN: US0902220
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Resource Relation:
Journal Name: Packaging, Transport, Storage and Security of Radioactive Material, 18:11-18; Journal Volume: 18
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; CASKS; CLOSURES; CONTAINMENT; FASTENERS; FLANGES; HYPOTHETICAL ACCIDENTS; IAEA; LICENSING; NUCLEAR FUELS; ORIENTATION; RADIOACTIVE MATERIALS; REGULATIONS; SPENT FUELS; STEELS; TRANSPORT

Citation Formats

Shah, M. J., Klymyshyn, Nicholas A., Adkins, Harold E., and Koeppel, Brian J. TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events. United States: N. p., 2007. Web. doi:10.1179/174651007X191125.
Shah, M. J., Klymyshyn, Nicholas A., Adkins, Harold E., & Koeppel, Brian J. TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events. United States. doi:10.1179/174651007X191125.
Shah, M. J., Klymyshyn, Nicholas A., Adkins, Harold E., and Koeppel, Brian J. Fri . "TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events". United States. doi:10.1179/174651007X191125.
@article{osti_951568,
title = {TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events},
author = {Shah, M. J. and Klymyshyn, Nicholas A. and Adkins, Harold E. and Koeppel, Brian J.},
abstractNote = {The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (10 CFR), Title 10, Part 71 [1]. Both the International Atomic Energy Agency regulations for transporting radioactive materials [2, paragraph 727], and 10 CFR 71.73 require casks to be evaluated for hypothetical accident conditions, which includes a 9-meter (m) (30-ft) drop-impact event onto a flat, essentially unyielding, horizontal surface, in the most damaging orientation. This paper examines the behavior of one of the NRC certified transportation casks, the TN-68 [3], for drop-impact events. The specific area examined is the behavior of the bolted connections in the cask body and the closure lid, which are significantly loaded during the hypothetical drop-impact event. Analytical work to evaluate the NRC-certified TN-68 spent fuel transport cask [3] for a 9-m (30-ft) drop-impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS® [4] and LS DYNA™ [5] finite-element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9-m (30-ft) free-drop hypothetical accident conditions, as specified in 10 CFR 71.73. Evaluation of the cask for puncture, caused by a free drop through a distance of 1-m (40-in.) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71.73, was not included in the current work, and will have to be addressed in the future. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the lid surfaces may occur under some conditions, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event.},
doi = {10.1179/174651007X191125},
journal = {Packaging, Transport, Storage and Security of Radioactive Material, 18:11-18},
number = ,
volume = 18,
place = {United States},
year = {Fri Mar 30 00:00:00 EDT 2007},
month = {Fri Mar 30 00:00:00 EDT 2007}
}