Published 1990 | Version v1
Book Metadata-only

Analysis and modeling of fission product release from heated uranium-aluminum plate-type reactor fuels

Creators

  • 1. Oak Ridge National Lab., TN (United States)

Description

This paper provides a perspective overview and analysis of volatile fission product release data obtained for U-Al reactor fuels, U-Alx (alloy and dispersed), U3O8-Al (dispersed), U3Si2-Al (dispersed), and U3Si-Al (dispersed). Several shortcomings in the experimental databases have been highlighted and areas of uncertainty identified related to extrapolation of correlation predictions. It is shown that fission product release characteristics for the U-Al reactor fuels are radically different from power reactor fuels. Significant dependencies that exist on ambient medium, rate of release, fuel-type and structure, fission product chemistry, and burnup are analyzed

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
The safety, status and future of non-commercial reactors and irradiation facilities
Imprint Pagination
830 p.
Journal Page Range
p. 368-370.

Conference

Title
American Nuclear Society (ANS) topical meeting on the safety, status and future of non-commercial reactors and irradiation facilities.
Dates
30 Sep - 4 Oct 1990.
Place
Boise, ID (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23035276
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALUMINIUM; BURNUP; CALCULATION METHODS; FISSION PRODUCT RELEASE; MATHEMATICAL MODELS; NUCLEAR FUELS; TEMPERATURE DEPENDENCE; TIME DEPENDENCE; URANIUM
Descriptors DEC
ACTINIDES; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; REACTOR MATERIALS

Optional Information

Secondary number(s)
CONF-900917--.