The thermal analysis of BR-100: A barge/rail nuclear spent fuel transportation container

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:7310125

Copsey, A B

B W Fuel Company is designing a spent-fuel container called BR-100 that can be used for either barge or rail transport. This paper presents the thermal design and analysis. Both normal operation and hypothetical accident thermal transient conditions are evaluated. The BR-100 cask has a concrete layer than contains free water. During a hypothetical accident, the free water vaporizes and flows from the cask, removing a significant amount of thermal transient energy. The BR-100 transportation package meets the thermal requirements of 10CFR71. It additionally offers substantial margins to established material temperature limits.

• Research Organization: B and W Fuel Co., Lynchburg, VA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC07-88ID12701
• OSTI ID: 7310125
• Report Number(s): EGG-M-91504; CONF-920430-102; ON: DE92017900
• Resource Relation: Conference: 3. international high level radioactive waste management (IHLRWM) conference, Las Vegas, NV (United States), 12-16 Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
HEAT TRANSFER
P CODES
SPENT FUEL CASKS
THERMAL ANALYSIS
ACCIDENTS
DESIGN
HEAT FLUX
RISK ASSESSMENT
WASTE TRANSPORTATION
CASKS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
MANAGEMENT
TRANSPORT
WASTE MANAGEMENT
050900* - Nuclear Fuels- Transport
Handling
& Storage
420204 - Engineering- Shipping Containers
052002 - Nuclear Fuels- Waste Disposal & Storage