BR-100 Spent Fuel Shipping Cask Development
Conference
·
OSTI ID:6496188
- B&W Fuel Company, Lynchburg, VA (United States)
Continued public acceptance of commercial nuclear power is contingent to a large degree on the US Department of Energy (DOE) establishing an integrated waste management system for spent nuclear fuel. As part of the from-reactor transportation segment of this system, the B&W Fuel Company (BWFC) is under contract to the DOE to develop a spent-fuel cask that is compatible with both rail and barge modes of transportation. Innovative design approaches were the keys to achieving a cask design that maximizes payload capacity and cask performance. The result is the BR-100, a 100-ton rail/barge cask with a capacity of 21 PWR or 52 BWR ten-year cooled, intact fuel assemblies.
- Research Organization:
- B&W Fuel Company, Lynchburg, VA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC07-88ID12701
- OSTI ID:
- 6496188
- Report Number(s):
- EGG-M-89418; CONF-900406--76; ON: DE91001940
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
420204 -- Engineering-- Shipping Containers
A CODES
BWR TYPE REACTORS
Boiling Water Reactor (BWR)
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
DESIGN
ENERGY SOURCES
FUEL ASSEMBLIES
FUELS
Fuel Baskets Designs
IMPACT STRENGTH
K CODES
LAND TRANSPORT
Life Cost Cycle (LCC) Analysis
MANAGEMENT
MARITIME TRANSPORT
MATERIALS
MECHANICAL PROPERTIES
NUCLEAR FUELS
Neutron Shield
Nuclear Criticality Safety Program (NCSP)
PHYSICAL PROPERTIES
PWR TYPE REACTORS
Pressurized Water Reactor (PWR)
RAIL TRANSPORT
REACTOR MATERIALS
REACTORS
Rail/Barge Cask
SPENT FUEL CASKS
SPENT FUELS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSPORT
Thermal Switch
WASTE MANAGEMENT
WASTE TRANSPORTATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
420204 -- Engineering-- Shipping Containers
A CODES
BWR TYPE REACTORS
Boiling Water Reactor (BWR)
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
DESIGN
ENERGY SOURCES
FUEL ASSEMBLIES
FUELS
Fuel Baskets Designs
IMPACT STRENGTH
K CODES
LAND TRANSPORT
Life Cost Cycle (LCC) Analysis
MANAGEMENT
MARITIME TRANSPORT
MATERIALS
MECHANICAL PROPERTIES
NUCLEAR FUELS
Neutron Shield
Nuclear Criticality Safety Program (NCSP)
PHYSICAL PROPERTIES
PWR TYPE REACTORS
Pressurized Water Reactor (PWR)
RAIL TRANSPORT
REACTOR MATERIALS
REACTORS
Rail/Barge Cask
SPENT FUEL CASKS
SPENT FUELS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSPORT
Thermal Switch
WASTE MANAGEMENT
WASTE TRANSPORTATION
WATER COOLED REACTORS
WATER MODERATED REACTORS