A computer code for calculation of radioactive nuclide generation and depletion, decay heat and γ ray spectrum. FPGS90
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
In a nuclear reactor radioactive nuclides are generated and depleted with burning up of nuclear fuel. The radioactive nuclides, emitting γ ray and β ray, play role of radioactive source of decay heat in a reactor and radiation exposure. In safety evaluation of nuclear reactor and nuclear fuel cycle, it is needed to estimate the number of nuclides generated in nuclear fuel under various burn-up condition of many kinds of nuclear fuel used in a nuclear reactor. FPGS90 is a code calculating the number of nuclides, decay heat and spectrum of emitted γ ray from fission products produced in a nuclear fuel under the various kinds of burn-up condition. The nuclear data library used in FPGS90 code is the library 'JNDC Nuclear Data Library of Fission Products - second version -', which is compiled by working group of Japanese Nuclear Data Committee for evaluating decay heat in a reactor. The code has a function of processing a so-called evaluated nuclear data file such as ENDF/B, JENDL, ENSDF and so on. It also has a function of making figures of calculated results. Using FPGS90 code it is possible to do all works from making library, calculating nuclide generation and decay heat through making figures of the calculated results. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
27056731.pdf
Files
(5.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 226 p.
- Report number
- JAERI-Data/Code--95-014
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27056731
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AFTER-HEAT; F CODES; FISSION YIELD; GAMMA SPECTRA; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; RADIATION PROTECTION; REACTOR SAFETY; TRANSMUTATION
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR REACTION YIELD; REACTOR MATERIALS; SAFETY; SPECTRA; YIELDS