Calculation of criticality condition data for single-unit homogeneous uranium materials in six chemical forms
- 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
Description
Single-unit criticality condition data were calculated for homogeneous uranium materials in six chemical forms for revision of the Data Collection appendix to the Nuclear Criticality Safety Handbook. The calculated criticality condition data were the estimated critical and the estimated lower-limit critical masses and volumes of spheres, diameters of infinitely-long cylinders and thicknesses of infinite-area slabs of uranium materials in six chemical forms encountered in criticality safety evaluation of nuclear fuel cycle facilities. The chemical forms were U-H2O, UO2-H2O, UO2F2, UO2(NO3)2, ADU-H2O and UF6-HF, the first and last ones of which were not dealt with the Data Collection. The calculations were made with the continuous-energy Monte Carlo criticality calculation code MVP and the Japanese Evaluated Nuclear Data Library JENDL-3.2. The values and precision of the present calculations are discussed in comparison with previous results. (author)
Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 43
- Journal Issue
- 11
- Journal Page Range
- p. 1406-1413
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53076826
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- CALCULATION METHODS; CHEMICAL STATE; CRITICAL MASS; CRITICAL SIZE; CRITICALITY; FUEL CYCLE CENTERS; M CODES; NUCLEAR DATA COLLECTIONS; SAFETY; URANIUM COMPOUNDS; URANIUM CONCENTRATES
- Descriptors DEC
- ACTINIDE COMPOUNDS; COMPUTER CODES; MASS; NUCLEAR FACILITIES; ORE CONCENTRATES; ORES; SIZE; URANIUM ORES
Optional Information
- Notes
- 30 refs., 10 figs., 3 tabs.; This record replaces 38044246