Conversion feasibility studies for the Grenoble high flux reactor
Feasibility studies for conversion of the High Flux Reactor (RHF) at Grenoble France have been performed at the Argonne National Laboratory in cooperation with the Institut Laue-Langevin (ILL). The uranium densities required for conversion of the RHF to reduced enrichment fuels were computed to be 7.9 g/cm{sup 3} with 20% enrichment, 4.8 g/cm{sup 3} with 29% enrichment, and 2.8 g/cm{sup 3} with 45% enrichment. Thermal flux reductions at the peak in the heavy water reflector were computed to be 3% with 45% enriched fuel and 7% with 20% enriched fuel. In each case, the reactor's 44 day cycle length was preserved and no changes were made in the fuel element geometry. If the cladding thickness could be reduced from 0.38 mm to 0.30 mm, the required uranium density with 20% enrichment would be about 6.0 g/cm{sup 3} and the thermal flux reduction at the peak in the heavy water reflector would be about 7%. Significantly higher uranium densities are required in the RHF than in heavy water reactors with more conventional designs because the neutron spectrum is much harder in the RHF. Reduced enrichment fuels with the uranium densities required for use in the RHF are either not available or are not licensable at the present time. 6 refs., 6 figs., 3 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- ACDA; DOE/MA
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5498205
- Report Number(s):
- CONF-8909141-3; ON: DE90001442; TRN: 89-031429
- Resource Relation:
- Conference: 12. international meeting on reduced enrichment for research and test reactors, Berlin (Germany, F.R.), 10-13 Sep 1989
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
GRENOBLE REACTOR
NUCLEAR FUELS
COMPARATIVE EVALUATIONS
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D CODES
DENSITY
DR-3 REACTOR
FEASIBILITY STUDIES
MEASURING METHODS
NUMERICAL DATA
POWER GENERATION
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ELEMENTS
ENERGY SOURCES
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ENRICHED URANIUM REACTORS
FUELS
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IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
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PHYSICAL PROPERTIES
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