Published 2004
| Version v1
Miscellaneous
A study on the fabrication of dry recycling nuclear fuel pellets by using simulated spent PWR fuel of high burnup
- 1. KAERI, Taejon (Korea, Republic of)
Description
To study the fabrication characteristics of dry recycling nuclear fuel using spent PWR fuel with high burnup of 60,000 MWd/tU, the fission products of spent PWR fuel was analyzed by ORIGEN-2 code. Simulated spent PWR fuel pellets were fabricated by using UO2 powder added by the simulated fission products. The simulated dry-recycling-fuel pellets were fabricated by dry recycling fuel fabrication flow including 3 cycle treated OREOX(Oxidation and REduction of OXide fuel) process. As the results of experiments, the densities of sintered pellets ranged from 95 % to 98 % of theoretical density at 1700 .deg. C and 1750 .deg. C of sintering temperature. The grain size of the pellets ranged from 5 to 6 μm
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [7 p.]
Conference
- Title
- 2004 spring meeting of the KNS
- Dates
- 27-28 May 2004
- Place
- Gyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35100626
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; FABRICATION; FISSION PRODUCTS; FUEL PELLETS; GRAIN SIZE; NUCLEAR FUELS; PWR TYPE REACTORS; RECYCLING; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; MICROSTRUCTURE; NUCLEAR FUELS; PELLETS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SIZE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 3 figs, 4 tabs