Published October 1989 | Version v1
Report

General philosophy on fuel management for burnup credit application

Creators

Description

It has become clear to many of those who have studied burnup credit applications that one of the keys to the acceptance of this design consideration is fuel management. Few doubt the physics of reduced reactivity as a result of fission product poisoning and fissile material depletion. And clearly, few question our current or future ability to predict the keff of a fuel array within a cask. At issue is our confidence in the fuel management systems of the nuclear utilities that ensure that specification fuel is loaded into the cask or, perhaps more correctly, the items that assure that nonspecification fuel is not loaded into the cask. Non-specification is defined here as fresh or burned fuel with reactivity that exceeds the cask design basis. Incidentally, this definition should apply equally to burnup credit as it does to the fresh fuel assumption since misloading errors can occur in either case, although the probabilities of such occurrences are extremely low

Additional details

Publishing Information

Imprint Title
Proceedings of a workshop on the use of burnup credit in spent fuel transport casks
Imprint Pagination
339 p.
Journal Page Range
p. 197-201.
Report number
SAND--89-0018

Conference

Title
U.S. Department of Energy workshop on the use of burnup credit in spent fuel transport casks.
Dates
21-22 Feb 1988.
Place
Washington, DC (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21049992
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; ERRORS; FISSILE MATERIALS; FUEL MANAGEMENT; REACTIVITY; SPENT FUELS
Descriptors DEC
ENERGY SOURCES; FISSIONABLE MATERIALS; FUELS; MANAGEMENT; MATERIALS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; REACTOR MATERIALS

Optional Information

Secondary number(s)
TTC--0884; CONF-880251--.