Published 1988
| Version v1
Report
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LEU fuel cycle analyses for the Belgian BR2 Research Reactor
Description
Equilibrium fuel cycle characteristics were calculated for reference HEU and two proposed LEU fuel cycles using an 11-group diffusion-theory neutron flux solution in hexagonal-Z geometry. The diffusion theory model was benchmarked with a detailed Monte Carlo core model. The two proposed LEU fuel designs increased the 235U loading 20% and the fuel meat volume 51%. The first LEU design used 10B as a burnable absorber. Either proposed LEU fuel element would provide equilibrium fuel cycle characteristics similar to those of the HEU fuel cycle. Irradiation rates of Co control followers and Ir disks in the center of the core were reduced 6 ± 1% in the LEU equilibrium core compared to reference HEU core. 11 refs., 4 figs., 5 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90010403; OSTI; INIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- CONF-8809221--8
Conference
- Title
- International meeting on reduced enrichment for research and test reactors (RERTR).
- Dates
- 18-24 Sep 1988.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21059690
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BR-2 REACTOR; CROSS SECTIONS; D CODES; DIFFUSION; E CODES; FUEL CYCLE; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; NEUTRON ABSORBERS; NEUTRON FLUX; SLIGHTLY ENRICHED URANIUM; V CODES
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MATERIALS TESTING REACTORS; METALS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38