Published July 1994 | Version v1
Report Open

A study on the radioactive waste management for DUPIC fuel cycle -A study on the direct use of spent PWR fuel in CANDU-

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)

Name Size Download all
md5:c6766e91334d98c5aabc1d4bf120c40c
3.8 MB Preview Download

Additional details

Publishing Information

Imprint Pagination
129 p.
Report number
KAERI/RR--1325/93