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AbstractAbstract
[en] 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/cm3 with 20% enrichment, 4.8 g/cm3 with 29% enrichment, and 2.8 g/cm3 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/cm3 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
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Source
1989; 23 p; 12. international meeting on reduced enrichment for research and test reactors; Berlin (Germany, F.R.); 10-13 Sep 1989; CONTRACT W-31109-ENG-38; Available from NTIS, PC A03/MF A01 as DE90001442; OSTI; INIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference; Numerical Data
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Country of publication
COMPARATIVE EVALUATIONS, COMPUTERIZED SIMULATION, D CODES, DENSITY, DR-3 REACTOR, FEASIBILITY STUDIES, GRENOBLE REACTOR, MEASURING METHODS, NUCLEAR FUELS, NUMERICAL DATA, POWER GENERATION, R CODES, REACTOR CONTROL SYSTEMS, REACTOR COOLING SYSTEMS, REACTOR CORES, RESEARCH PROGRAMS, SLIGHTLY ENRICHED URANIUM, TEMPERATURE DEPENDENCE
ACTINIDES, COMPUTER CODES, CONTROL SYSTEMS, COOLING SYSTEMS, DATA, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, EVALUATION, FUELS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INFORMATION, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, MATERIALS, MATERIALS TESTING REACTORS, METALS, PHYSICAL PROPERTIES, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SIMULATION, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, URANIUM
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