A new swelling model and its application to uranium silicide research reactor fuel

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

OSTI ID:6981935

Hofman, G L; Rest, J; Snelgrove, J L

This document discusses a new version of the dispersion fuel behavior model currently being incorporated in DART, which has been generated. The model's description of fuel swelling - more specifically, the evaluation of fission-gas bubble morphology - is significantly improved. Although some of the assumptions underlying the basic model are derived from systems other than U[sub 3]Si[sub 2], it represents a physically realistic interpretation of the observed irradiation behavior of U[sub 3]Si[sub 2] over a wide range of fission densities and fission rates.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6981935
• Report Number(s): ANL/EP/CP-77801; CONF-9209266-3; ON: DE93002932
• Resource Relation: Conference: 1992 international meeting on reduced enrichment for research and test reactors, Roskilde (Denmark), 27 Sep - 1 Oct 1992
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
RESEARCH REACTORS
NUCLEAR FUELS
URANIUM SILICIDES
SWELLING
D CODES
HIGHLY ENRICHED URANIUM
PERFORMANCE
SLIGHTLY ENRICHED URANIUM
ACTINIDE COMPOUNDS
ACTINIDES
COMPUTER CODES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FUELS
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SILICIDES
SILICON COMPOUNDS
URANIUM
URANIUM COMPOUNDS
050700* - Nuclear Fuels- Fuels Production & Properties
990200 - Mathematics & Computers
350200 - Arms Control- Proliferation- (1987-)