Testing ENDF/B-V data for thermal reactors
Description
Lattice parameters have been calculated for some thermal reactor benchmark lattices using ENDF/B-V data. These lattices were TRX-1, -2; BAPL-UO2-1,-2,-3; BNL-ThO2-233UO2-H20-1,-2,-3; MIT-4,-5,-6; and PNL-31,-33,-35 (infinite lattices). In addition, parameters were calculated for 3 ZEEP lattices, 3 High-Conversion U02-H20 lattices, and 7 BNL-Th02-233U02-D20 lattices. These calculations were made using the integral transport cell code RAHAB with the resonance reaction rates obtained using the OZMA code operating in the discrete ordinate mode. This code calculates the resonance rates allowing for the interaction of all resonances. Four group reaction rates for use in method comparisons are given for several lattices. The author discusses the use of the OZMA code for these calculations, including the choice of options and the orders of the angular quadratures, and compares results obtained using the CRNL thermal scattering data with those obtained using ENDF/B data
Availability note (English)
MF available from INIS under the Report Number.Files
15044186.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 119 p.
- Report number
- AECL--7690
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 15044186
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BENCHMARKS; COMPILED DATA; COMPUTER CALCULATIONS; FUEL CANS; INTERLABORATORY COMPARISONS; MIXED OXIDE FUELS; NEUTRON FLUX; NEUTRON REACTIONS; NUCLEAR REACTION KINETICS; REACTOR LATTICES; REACTOR MATERIALS; THERMAL REACTORS; TOTAL CROSS SECTIONS
- Descriptors DEC
- BARYON REACTIONS; CROSS SECTIONS; DATA; ENERGY SOURCES; FUELS; HADRON REACTIONS; INFORMATION; KINETICS; MATERIALS; NUCLEAR FUELS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; RADIATION FLUX; REACTION KINETICS; REACTORS; SOLID FUELS