A methodology for evaluating the response of spent fuel subjected to regulatory transportation accidents
Conference
·
OSTI ID:5899793
- ANATECH Research Corp., San Diego, CA (USA)
- Sandia National Labs., Albuquerque, NM (USA)
Spent fuel shipping casks in the US are designed to withstand a hypothetical event of a 9-meter drop upon an unyielding target under the regulatory requirements of Part 71 of Title 10 of the Code of Federal Regulations (10CFR71). The fuel response under this dynamic impact event constitutes a pivotal role in the source term assessment for spent fuel transport casks. The first step in evaluating the source term is the calculation of the fuel rod dynamic response. This paper illustrates an analysis methodology developed for determining the mechanical response of spent fuel in a transport cask subjected to impact loading. The analysis accounts for the structural interaction between the assemblies and basket, and between assembly hardware and fuel rods. The load transfer paths from the cask to the fuel assemblies depend strongly on the drop orientation. The three possible drop orientations are: (1) side drop; (2) end drop; and (3) corner drop (initial impact and slap down). Structural modeling and simulation of these drop orientations are described and example applications are presented. 2 refs., 6 figs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5899793
- Report Number(s):
- SAND-90-3110C; CONF-910817--1; ON: DE91008575
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
ACCIDENTS
ACTIVITY LEVELS
BENDING
BWR TYPE REACTORS
CASKS
CONTAINERS
DEFORMATION
FUEL ASSEMBLIES
FUEL ELEMENTS
IMPACT SHOCK
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
NORTH AMERICA
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
REGULATIONS
SANDIA LABORATORIES
SOURCE TERMS
SPACERS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
STRAINS
TESTING
TIME DEPENDENCE
TRANSPORT
US AEC
US DOE
US ERDA
US ORGANIZATIONS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
ACCIDENTS
ACTIVITY LEVELS
BENDING
BWR TYPE REACTORS
CASKS
CONTAINERS
DEFORMATION
FUEL ASSEMBLIES
FUEL ELEMENTS
IMPACT SHOCK
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
NORTH AMERICA
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
REGULATIONS
SANDIA LABORATORIES
SOURCE TERMS
SPACERS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
STRAINS
TESTING
TIME DEPENDENCE
TRANSPORT
US AEC
US DOE
US ERDA
US ORGANIZATIONS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS