Actions for LEU fuel cycle analyses for the Belgian BR2 Research Reactor [electronic resource].
LEU fuel cycle analyses for the Belgian BR2 Research Reactor [electronic resource].
- Published
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 1988.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (12 pages) : digital, PDF file
- Additional Creators
- Argonne National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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 ¹°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.
- Report Numbers
- E 1.99:conf-8809221-8
conf-8809221-8 - Subject(s)
- Other Subject(s)
- Br-2 Reactor
- Fuel Cycle
- Benchmarks
- Cross Sections
- D Codes
- Diffusion
- E Codes
- Fuel Elements
- Highly Enriched Uranium
- Neutron Absorbers
- Neutron Flux
- Slightly Enriched Uranium
- V Codes
- 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
- Note
- Published through SciTech Connect.
01/01/1988.
"conf-8809221-8"
"DE90010403"
International meeting on reduced enrichment for research and test reactors (RERTR), San Diego, CA (USA), 18-24 Sep 1988.
Deen, J.R.; Snelgrove, J.L. - Funding Information
- W-31109-ENG-38
View MARC record | catkey: 14803188