A new swelling model and its application to uranium silicide research reactor fuel
Conference
·
OSTI ID:10112484
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, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10112484
- 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; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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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
URANIUM SILICIDES
SWELLING
RESEARCH REACTORS
NUCLEAR FUELS
D CODES
HIGHLY ENRICHED URANIUM
SLIGHTLY ENRICHED URANIUM
PERFORMANCE
050700
990200
350200
FUELS PRODUCTION AND PROPERTIES
MATHEMATICS AND COMPUTERS
PROLIFERATION
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
URANIUM SILICIDES
SWELLING
RESEARCH REACTORS
NUCLEAR FUELS
D CODES
HIGHLY ENRICHED URANIUM
SLIGHTLY ENRICHED URANIUM
PERFORMANCE
050700
990200
350200
FUELS PRODUCTION AND PROPERTIES
MATHEMATICS AND COMPUTERS
PROLIFERATION