A study on the radioactive waste management for DUPIC fuel cycle -A study on the direct use of spent PWR fuel in CANDU-
Creators
- 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Description
The characteristics of the radioactive wastes coming from the DUPIC fuel manufacturing process were analyzed and evaluated. The release amounts of nuclides were estimated, and the characteristics of the oxides of semi-volatile nuclides such as Ru and Cs were analyzed and also these trapping and fixation technologies were assessed. The conceptual methods of experiment including apparatus and procedure were completed to define the vaporization behavior of nuclides. The gross α-activity and α-, γ-spectrum of irradiated zircaloy specimens from KORI unit 1 were analyzed and the press to test the compaction of hulls was manufactured. Ingestion hazard index for the disposal of spent DUPIC fuel were calculated using ORIGEN 2 code and compared with the disposal of once-through spent PWR and CANDU fuels, and then the index per kwh for DUPIC cycle was 1/8 ∼ 1/4 lower than that for once-through cycle. (Author)
Availability note (English)
MF available from INIS under the Report Number.Files
26011888.pdf
Files
(3.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 129 p.
- Report number
- KAERI/RR--1325/93
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 26011888
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- FISSILE MATERIALS; FUEL CYCLE; NUCLEAR FUELS; RADIOACTIVE WASTE MANAGEMENT; RUTHENIUM; SOLIDIFICATION; SPENT FUELS; VOLATILE MATTER
- Descriptors DEC
- ELEMENTS; ENERGY SOURCES; FISSIONABLE MATERIALS; FUELS; MANAGEMENT; MATERIALS; MATTER; METALS; PLATINUM METALS; REACTOR MATERIALS; TRANSITION ELEMENTS; WASTE MANAGEMENT