Published 1992 | Version v1
Report Restricted

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

Creators

Description

B ampersand 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

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92017900; NTIS; INIS; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
EGG-M--91504

Conference

Title
3. international high level radioactive waste management (IHLRWM) conference.
Dates
12-16 Apr 1992.
Place
Las Vegas, NV (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24010969
Subject category
S42: ENGINEERING; S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; CASKS; DESIGN; HEAT FLUX; HEAT TRANSFER; P CODES; RISK ASSESSMENT; THERMAL ANALYSIS; WASTE TRANSPORTATION
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; MANAGEMENT; WASTE MANAGEMENT

Optional Information

Contract/Grant/Project number
Contract AC07-88ID12701
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-920430--102.