Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts
The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.
- Research Organization:
- Yucca Mountain Project, Las Vegas, NV (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- NA
- OSTI ID:
- 899635
- Report Number(s):
- 000-00C-DS00-00600-000-00B, Rev 00B ECN 1; ENG.20050817.0015, DC# 45435; TRN: US0702202
- Country of Publication:
- United States
- Language:
- English
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