Published December 1975
| Version v1
Report
Irradiation experiments of recycled PuO2-UO2 fuels by SAXTON reactor, (5)
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
Description
The post-irradiation examination results of mixed oxide fuels irradiated in SAXTON reactor are used for the verification of a fuel performance analysis code ''ACTIVE-II'', and the performance of the fuels under irradiation is estimated by the ACTIVE-II code. (auth.)
Additional details
Additional titles
- Subtitle (English)
- Fuel performance analysis
Publishing Information
- Imprint Title
- Semi-annual progress report of Power Reactor and Nuclear Fuel Development Corporation, Tokai Works
- Journal Page Range
- p. 95-106.
- Report number
- PNCT--831-75-02
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8340967
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- A CODES; CRACKS; FISSION PRODUCTS; FUEL CANS; FUEL RODS; IRRADIATION; IRRADIATION PROCEDURES; NUCLEAR FUELS; PERFORMANCE; PLUTONIUM OXIDES; POWER DISTRIBUTION; RADIATION EFFECTS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; FUEL ELEMENTS; FUELS; ISOTOPES; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS