LEU fuel cycle analyses for the Belgian BR2 Research Reactor
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 {sup 235}U loading 20% and the fuel meat volume 51%. The first LEU design used {sup 10}B 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 {plus minus} 1% in the LEU equilibrium core compared to reference HEU core. 11 refs., 4 figs., 5 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6913685
- Report Number(s):
- CONF-8809221-8; ON: DE90010403
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210802* -- Nuclear Power Plants-- Economics-- Fuel Cycle
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BENCHMARKS
BR-2 REACTOR
COMPUTER CODES
CROSS SECTIONS
D CODES
DIFFUSION
E CODES
ELEMENTS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL CYCLE
FUEL ELEMENTS
HIGHLY ENRICHED URANIUM
IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
MATERIALS
MATERIALS TESTING REACTORS
METALS
NEUTRON ABSORBERS
NEUTRON FLUX
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
SLIGHTLY ENRICHED URANIUM
TANK TYPE REACTORS
THERMAL REACTORS
URANIUM
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS