Enrichment reduction of the FRG-1 research reactor
Description
The GKSS research centre is participating since 1980 in the national and international efforts on enrichment reduction to clarify the needs on safety and licensing issues, to decide on fuel tests, to perform fuel tests and conversion calculations. These efforts are being made within the IAEA working groups, the German AF-program and the GKSS R and D program. There are successfully tested fuel elements with 45% and 20% enrichment: UAIx, U3O8 and U3Si2 fuel meat; U-density up to 3,7 g U/cm3 and fission densities up to 1,25 x 1021 fission/cc (ex. Pu) and five U3Si2 fuel plates (ρ(U) 4,75 g U/cm3). A safety report for the conversion of the FRG-1 to LEU fuel (U3Si2, ρ = 37 g U/cm3) has been submitted to the licensing authority. After examining the safety report by independent experts (TUeV) and the licensing authority the license for the conversion has been granted in May 1988. The FRG-1 has been totally converted in 1991 to LEU fuel elements. All necessary tests have been performed in a three- week period. The conversion procedure includes a reduction in core size by a factor of two and the replacement of old oval control rods by fork type absorbers. Therefore the thermal neutron flux in beam tube positions could be increased by more than a factor of two. (author)
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Additional details
Publishing Information
- ISBN
- 979-8500-09-1
- Imprint Title
- Reduced Enrichment for Research and Test Reactors. Proceedings of the XIV international meeting
- Imprint Pagination
- 477 p.
- Journal Page Range
- p. 187-197
- Report number
- INIS-XA-C--006
Conference
- Title
- 14. international meeting on Reduced Enrichment for Research and Test Reactors
- Dates
- 4-7 Nov 1991
- Place
- Jakarta (Indonesia)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35047129
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; FRG-1 REACTOR; FUEL PLATES; NEUTRON FLUX; REACTOR CORES; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; THERMAL NEUTRONS; URANIUM ALLOYS; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDE COMPOUNDS; ACTINIDES; ALLOYS; BARYONS; CHALCOGENIDES; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FERMIONS; FUEL ELEMENTS; HADRONS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NEUTRONS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 1 fig., 1 tab