Published August 1989
| Version v1
Journal article
Validation of ORIGEN computer code by measurements on nuclear fuels of JPDR-1
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
The depletion and production amounts of U, Pu, transplutonium nuclides and fission products (FPs) measured on the fuel of JPDR-1 were corrected to take account of the performance history of irradiation and cooling using the results of three-dimensional nuclear-thermo-hydrodynamic and nuclide depletion and production calculations. Except a few nuclides, the corrected values proved to agree well with the values calculated by the ORIGEN computer code. Further enhancement of calculational accuracy calls for systematic re-evaluation of neutron cross sections on the basis of neutron spectrum in nuclear fuel. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 26
- Journal Issue
- 8
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 777-786
- ISSN
- 0022-3131
- CODEN
- JNSTA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 21007898
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- ACCURACY; ACTINIDES; BURNUP; BWR TYPE REACTORS; CROSS SECTIONS; FISSION PRODUCTS; ISOTOPE PRODUCTION; JPDR REACTOR; NEUTRON SPECTRA; NUCLEAR FUELS; O CODES; POWER DISTRIBUTION; SPATIAL DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; TRANSPLUTONIUM ELEMENTS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; ISOTOPES; MATERIALS; METALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SPECTRA; THERMAL REACTORS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS