Assessment of a U Product purity from Pyroprocessing Spent EBR-II Fuel
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Chungnam National University, Daejeon (Korea, Republic of)
- 3. Idaho National Laboratory, Idaho Falls (United States)
Description
A comprehensive analysis has been conducted on the purity of the uranium product generated from a pyroprocessing of EBR-II spent fuel. The analysis results were compared to the low-level waste criteria for both ROK and USA under a collaborative program between INL and KAERI. It is found that the US LLW definition does not include the activity from any U isotopes, but the Korean one does. The analysis results show that Pu-239 is the only alpha emitting isotope other than U isotopes that exceed the limit in the EBR-II U product. Pu contamination of the product seems to be drastically reduced in a preliminary test of the modified cathode process, and the further development of the proposed technology may be possible to meet the US LLW criteria.
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Radioactive Waste Society
- Journal Volume
- 7
- Journal Issue
- 3
- Series
- 10 refs, 4 figs, 3 tabs
- Journal Page Range
- p. 167-174
- ISSN
- 1738-1894
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42074828
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CONTAMINATION; LOW-LEVEL RADIOACTIVE WASTES; SPENT FUELS; URANIUM ISOTOPES
- Descriptors DEC
- ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; WASTES