Babcock and Wilcox BR-100 100-Ton Rail/Barge Spent Fuel Shipping Cask (Preliminary Design Report) (Vol. 2)
The purpose of this document is to provide information on burnup credit as applied to the preliminary design of the BR-100 shipping cask. There is a brief description of the preliminary basket design and the features used to maintain a critically safe system. Following the basket description is a discussion of various criticality analyses used to evaluate burnup credit. The results from these analyses are then reviewed in the perspective of fuel burnups expected to be shipped to either the final repository or a Monitored Retrievable Storage (MRS) facility. The hurdles to employing burnup credit in the certification of any cask are then outlines and reviewed. the last section gives conclusions reached as to burnup credit for the BR-100 cask, based on our analyses and experience. All information in this study refers to the cask configured to transport PWR fuel. Boiling Water Reactor (BWR) fuel satisfies the criticality requirements so that burnup credit is not needed. All calculations generated in the preparation of this report were based upon the preliminary design which will be optimized during the final design.
- Research Organization:
- B & W Fuel Co., Lynchburg, VA (United States)
- Sponsoring Organization:
- USDOE Office of Civilian Radioactive Waste Management (RW); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC07-88ID12701
- OSTI ID:
- 6750935
- Report Number(s):
- DOE/ID/12701--1-Vol.2; BW--51-1177082-02-Vol.2; ON: DE90013717
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
420204* -- Engineering-- Shipping Containers
BARGES
BURNUP
Boiling Water Reactor (BWR)
CASKS
CONTAINERS
CONTAINMENT
CRITICALITY
Cask System Development Program
ENERGY SOURCES
FUELS
LAND TRANSPORT
MAINTENANCE
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
PACKAGING RULES
RAIL TRANSPORT
REACTOR MATERIALS
REGULATIONS
SCHEDULES
SHIELDING
SPECIFICATIONS
SPENT FUEL CASKS
SPENT FUELS
STANDARDS
TESTING
THERMAL ANALYSIS
TRANSPORT