Elastic/Plastic Drop Analysis Using Finite Element Techniques
Abstract
A Spent Nuclear Fuel (SNF) can, which is called the High Integrity Can (HIC), is being designed at the Idaho National Engineering and Environmental Laboratory (INEEL). Its intended use is to contain SNF sent to the Idaho Nuclear Technology and Engineering Center (INTEC). INTEC will then do the final work with the HIC to send it to the repository at Yucca Mountain, Nevada, for long-term storage. One portion of the analysis, which was required for the HIC, was accidental drop scenarios. This consisted of 19 simulated drops from a height of 30-feet with impact on a flat rigid surface. Elastic/plastic analyses were performed for the simulated drops. Additionally, two elastic/plastic analyses were performed for drops from a height of 17-feet with impact on a rigid surface having a narrow-raised portion across its center. The purpose of the analyses was to determine if any breach occurred which opened a crack wider than 0.05-inches from these drop scenarios. Also, some plastic deformations were needed from certain drop scenarios to support the Criticality Safety documentation. The analytical results for the simulated drop scenarios showed that, though the seal in the lid may be broken, no 0.05-inch breach occurred. Also, the deformations for Criticalitymore »
- Authors:
-
- Lockheed Martin Idaho Technologies Company, Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Lockheed Martin Idaho Technologies Company, Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Assistant Secretary for Environmental Management (EM); USDOE Idaho Operations Office (IO)
- OSTI Identifier:
- 8252
- Report Number(s):
- INEEL/CON-99-00259
TRN: US0101957
- DOE Contract Number:
- AC07-94ID13223
- Resource Type:
- Conference
- Resource Relation:
- Conference: 1999 ASME Pressure Vessels and Piping Conference, Boston, MA (United States), 1-5 Aug 1999; Other Information: PBD: 1 Aug 1999
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; SPENT FUEL CASKS; IMPACT SHOCK; IMPACT STRENGTH; IMPACT TESTS; ELASTICITY; PLASTICITY; CRITICALITY; PERFORMANCE; Nuclear Criticality Safety Program (NCSP); Spent Nuclear Fuel (SNF); High Integrity Can (HIC); Irradiated Fuel Storage Facility (IFSF) Canister; Yucca Mountain; Finite Element Models; ABAQUS/Explicit Model
Citation Formats
Spears, Robert E. Elastic/Plastic Drop Analysis Using Finite Element Techniques. United States: N. p., 1999.
Web.
Spears, Robert E. Elastic/Plastic Drop Analysis Using Finite Element Techniques. United States.
Spears, Robert E. 1999.
"Elastic/Plastic Drop Analysis Using Finite Element Techniques". United States. https://www.osti.gov/servlets/purl/8252.
@article{osti_8252,
title = {Elastic/Plastic Drop Analysis Using Finite Element Techniques},
author = {Spears, Robert E.},
abstractNote = {A Spent Nuclear Fuel (SNF) can, which is called the High Integrity Can (HIC), is being designed at the Idaho National Engineering and Environmental Laboratory (INEEL). Its intended use is to contain SNF sent to the Idaho Nuclear Technology and Engineering Center (INTEC). INTEC will then do the final work with the HIC to send it to the repository at Yucca Mountain, Nevada, for long-term storage. One portion of the analysis, which was required for the HIC, was accidental drop scenarios. This consisted of 19 simulated drops from a height of 30-feet with impact on a flat rigid surface. Elastic/plastic analyses were performed for the simulated drops. Additionally, two elastic/plastic analyses were performed for drops from a height of 17-feet with impact on a rigid surface having a narrow-raised portion across its center. The purpose of the analyses was to determine if any breach occurred which opened a crack wider than 0.05-inches from these drop scenarios. Also, some plastic deformations were needed from certain drop scenarios to support the Criticality Safety documentation. The analytical results for the simulated drop scenarios showed that, though the seal in the lid may be broken, no 0.05-inch breach occurred. Also, the deformations for Criticality Safety documentation were calculated and show on the applicable output plots.},
doi = {},
url = {https://www.osti.gov/biblio/8252},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Aug 01 00:00:00 EDT 1999},
month = {Sun Aug 01 00:00:00 EDT 1999}
}