Abstract
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 {alpha}-activity and {alpha}-, {gamma}-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 {approx} 1/4 lower than that for once-through cycle. (Author).
Park, Hyeon Soo;
Chun, Kwan Sik;
Kim, Jong Ho;
Cho, Yeong Hyeon;
Paek, Seung Uh;
Kang, Hee Seok;
Na, Jeong Won;
Choi, Jong Won;
Lee, Hu Keun;
Park, Keun Il;
Yang, Seung Yeong
[1]
- Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Citation Formats
Park, Hyeon Soo, Chun, Kwan Sik, Kim, Jong Ho, Cho, Yeong Hyeon, Paek, Seung Uh, Kang, Hee Seok, Na, Jeong Won, Choi, Jong Won, Lee, Hu Keun, Park, Keun Il, and Yang, Seung Yeong.
A study on the radioactive waste management for DUPIC fuel cycle - A study on the direct use of spent PWR fuel in CANDU.
Korea, Republic of: N. p.,
1994.
Web.
Park, Hyeon Soo, Chun, Kwan Sik, Kim, Jong Ho, Cho, Yeong Hyeon, Paek, Seung Uh, Kang, Hee Seok, Na, Jeong Won, Choi, Jong Won, Lee, Hu Keun, Park, Keun Il, & Yang, Seung Yeong.
A study on the radioactive waste management for DUPIC fuel cycle - A study on the direct use of spent PWR fuel in CANDU.
Korea, Republic of.
Park, Hyeon Soo, Chun, Kwan Sik, Kim, Jong Ho, Cho, Yeong Hyeon, Paek, Seung Uh, Kang, Hee Seok, Na, Jeong Won, Choi, Jong Won, Lee, Hu Keun, Park, Keun Il, and Yang, Seung Yeong.
1994.
"A study on the radioactive waste management for DUPIC fuel cycle - A study on the direct use of spent PWR fuel in CANDU."
Korea, Republic of.
@misc{etde_10112212,
title = {A study on the radioactive waste management for DUPIC fuel cycle - A study on the direct use of spent PWR fuel in CANDU}
author = {Park, Hyeon Soo, Chun, Kwan Sik, Kim, Jong Ho, Cho, Yeong Hyeon, Paek, Seung Uh, Kang, Hee Seok, Na, Jeong Won, Choi, Jong Won, Lee, Hu Keun, Park, Keun Il, and Yang, Seung Yeong}
abstractNote = {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 {alpha}-activity and {alpha}-, {gamma}-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 {approx} 1/4 lower than that for once-through cycle. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}
title = {A study on the radioactive waste management for DUPIC fuel cycle - A study on the direct use of spent PWR fuel in CANDU}
author = {Park, Hyeon Soo, Chun, Kwan Sik, Kim, Jong Ho, Cho, Yeong Hyeon, Paek, Seung Uh, Kang, Hee Seok, Na, Jeong Won, Choi, Jong Won, Lee, Hu Keun, Park, Keun Il, and Yang, Seung Yeong}
abstractNote = {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 {alpha}-activity and {alpha}-, {gamma}-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 {approx} 1/4 lower than that for once-through cycle. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}