Radioactivity analysis of DUPIC fuel fabrication process according to burn-up and cooling time
- 1. DUPIC Fuel Facility Development Team, Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)
Description
A radioactivity analysis of OREOX and the sintering steps for the DUPIC fuel fabrication process has been conducted. This study utilized ORIGEN2 code to calculate and analyze the radioactivity of spent fuels for various burn-up and cooling times. The analysis results have shown that the activity reduction of spent fuels after DUPIC fuel fabrication process was 40∝51% and higher with longer burn-up and cooling times. This study also shows that the distribution of gaseous waste generated from OREOX process is mainly attributed to Kr, Ru and H-3, regardless of burn-up and cooling times. On the other hand, in the off-gas of the sintering process, the radioactivity distribution of Cs is more than 98%, regardless of burn-up and cooling times. (orig.)
Additional details
Publishing Information
- Journal Title
- Key Engineering Materials
- Journal Volume
- 277-279
- Series
- On the convergence of bio-, information-, environmental-, energy-, space- and nano-technologies
- Journal Page Range
- p. 475-480
- ISSN
- 1013-9826
- CODEN
- KEMAEY
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 36024521
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ANTIMONY ISOTOPES; BURNUP; CESIUM ISOTOPES; COOLING; FISSION PRODUCTS; GASEOUS WASTES; KRYPTON ISOTOPES; O CODES; RADIOACTIVE EFFLUENTS; RADIOACTIVITY; RUTHENIUM ISOTOPES; SINTERING; SPENT FUELS; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COMPUTER CODES; ENERGY SOURCES; FABRICATION; FUELS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATERIALS; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; REACTOR MATERIALS; WASTES; YEARS LIVING RADIOISOTOPES