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The development of nuclear fuel for the future

Technical Report:

Abstract

Goal is to develop nuclear fuels which can improve the safety and economics of nuclear power generation and enhance the effective use of uranium resources. The fuels are aimed for successive power plants after the year 2000. To achieve these goals, it is necessary to analyse characteristics of advanced concept fuels based on currently available fuel design and manufacturing technology and to establish new design and manufacturing technology for the new concept fuels. This first year of the project focused on 1) technical feasibility evaluation of application of existing technology to advanced concept fuel such as extra-high BU fuel or other improved feature fuel, 2) analysis of domestic and foreign circumstances for advanced concept fuel development and drawing-out of plans for its development, and 3) securing of basic technology for development. For analysis of nuclear fuel characteristics, expected change in design parameters at high BU has been evaluated and fuel cycle evaluation models were improved for development of fuel cycle strategy with high BU fuel. For verification and improvement of design methodology, technical feasibility of application of the existing nuclear design system to advanced fuel has been analysed and thermal-hydraulic analysis methodology is under improvement for more thermal design margin.  More>>
Publication Date:
May 01, 1993
Product Type:
Technical Report
Report Number:
KAERI/RR-1247/93
Reference Number:
SCA: 220300; 050700; PA: AIX-26:011200; EDB-95:028383; SN: 95001324065
Resource Relation:
Other Information: PBD: May 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NUCLEAR FUELS; BURNUP; COMPUTER CODES; CORROSION; FABRICATION; FUEL ASSEMBLIES; FUEL CYCLE; POWDERS; PWR TYPE REACTORS; REACTOR CORES; SPENT FUELS; THERMODYNAMIC PROPERTIES; ZIRCALOY; 220300; 050700; FUEL ELEMENTS; FUELS PRODUCTION AND PROPERTIES
OSTI ID:
10113965
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612813; TRN: KR9400107011200
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
41 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Sohn, Dong Seong, Kim, Shi Hwan, Lim, Kap Soon, Yang, Myeong Soon, Lee, Yeong Uh, Kim, Yeong Jin, Ju, Hyeong Kook, Oh, Soo Yeol, Kim, Yeong Il, No, Jae Man, Lee, Jae Kyeong, Koo, Yang Heon, Song, Keun Uh, Lee, Hee Seong, Kim, Keung Koo, Jeong, Hyeong Kook, Hwang, Dae Heon, Yoo, Yeon Jong, Jang, Jong Hwa, Kim, Jeong Do, Kil, Chung Seop, Choi, Chang Beom, Bae, Ki Kwang, Kim, Han Soo, Choi, Meong Seon, Kim, Hyeong Seop, Lee, Jeong Won, Park, Chun Ho, Jeong, Sang Tae, Park, Jin Ho, Kim, Eung Ho, Kim, Tae Jun, Jeong, Keong Chai, Uh, Moon Sik, Hong, Soon Bok, and Kim, Yeon Koo. The development of nuclear fuel for the future. Korea, Republic of: N. p., 1993. Web.
Sohn, Dong Seong, Kim, Shi Hwan, Lim, Kap Soon, Yang, Myeong Soon, Lee, Yeong Uh, Kim, Yeong Jin, Ju, Hyeong Kook, Oh, Soo Yeol, Kim, Yeong Il, No, Jae Man, Lee, Jae Kyeong, Koo, Yang Heon, Song, Keun Uh, Lee, Hee Seong, Kim, Keung Koo, Jeong, Hyeong Kook, Hwang, Dae Heon, Yoo, Yeon Jong, Jang, Jong Hwa, Kim, Jeong Do, Kil, Chung Seop, Choi, Chang Beom, Bae, Ki Kwang, Kim, Han Soo, Choi, Meong Seon, Kim, Hyeong Seop, Lee, Jeong Won, Park, Chun Ho, Jeong, Sang Tae, Park, Jin Ho, Kim, Eung Ho, Kim, Tae Jun, Jeong, Keong Chai, Uh, Moon Sik, Hong, Soon Bok, & Kim, Yeon Koo. The development of nuclear fuel for the future. Korea, Republic of.
Sohn, Dong Seong, Kim, Shi Hwan, Lim, Kap Soon, Yang, Myeong Soon, Lee, Yeong Uh, Kim, Yeong Jin, Ju, Hyeong Kook, Oh, Soo Yeol, Kim, Yeong Il, No, Jae Man, Lee, Jae Kyeong, Koo, Yang Heon, Song, Keun Uh, Lee, Hee Seong, Kim, Keung Koo, Jeong, Hyeong Kook, Hwang, Dae Heon, Yoo, Yeon Jong, Jang, Jong Hwa, Kim, Jeong Do, Kil, Chung Seop, Choi, Chang Beom, Bae, Ki Kwang, Kim, Han Soo, Choi, Meong Seon, Kim, Hyeong Seop, Lee, Jeong Won, Park, Chun Ho, Jeong, Sang Tae, Park, Jin Ho, Kim, Eung Ho, Kim, Tae Jun, Jeong, Keong Chai, Uh, Moon Sik, Hong, Soon Bok, and Kim, Yeon Koo. 1993. "The development of nuclear fuel for the future." Korea, Republic of.
@misc{etde_10113965,
title = {The development of nuclear fuel for the future}
author = {Sohn, Dong Seong, Kim, Shi Hwan, Lim, Kap Soon, Yang, Myeong Soon, Lee, Yeong Uh, Kim, Yeong Jin, Ju, Hyeong Kook, Oh, Soo Yeol, Kim, Yeong Il, No, Jae Man, Lee, Jae Kyeong, Koo, Yang Heon, Song, Keun Uh, Lee, Hee Seong, Kim, Keung Koo, Jeong, Hyeong Kook, Hwang, Dae Heon, Yoo, Yeon Jong, Jang, Jong Hwa, Kim, Jeong Do, Kil, Chung Seop, Choi, Chang Beom, Bae, Ki Kwang, Kim, Han Soo, Choi, Meong Seon, Kim, Hyeong Seop, Lee, Jeong Won, Park, Chun Ho, Jeong, Sang Tae, Park, Jin Ho, Kim, Eung Ho, Kim, Tae Jun, Jeong, Keong Chai, Uh, Moon Sik, Hong, Soon Bok, and Kim, Yeon Koo}
abstractNote = {Goal is to develop nuclear fuels which can improve the safety and economics of nuclear power generation and enhance the effective use of uranium resources. The fuels are aimed for successive power plants after the year 2000. To achieve these goals, it is necessary to analyse characteristics of advanced concept fuels based on currently available fuel design and manufacturing technology and to establish new design and manufacturing technology for the new concept fuels. This first year of the project focused on 1) technical feasibility evaluation of application of existing technology to advanced concept fuel such as extra-high BU fuel or other improved feature fuel, 2) analysis of domestic and foreign circumstances for advanced concept fuel development and drawing-out of plans for its development, and 3) securing of basic technology for development. For analysis of nuclear fuel characteristics, expected change in design parameters at high BU has been evaluated and fuel cycle evaluation models were improved for development of fuel cycle strategy with high BU fuel. For verification and improvement of design methodology, technical feasibility of application of the existing nuclear design system to advanced fuel has been analysed and thermal-hydraulic analysis methodology is under improvement for more thermal design margin. For review of state-of-the-art and study of developmental plans, trends and circumstances of nuclear fuel development in foreign countries have been analysed and several domestic developmental plans were identified. For development of advanced nuclear fuel fabrication technology, preliminary experiments for mixing of additives with UO{sub 2} powder were performed and state-of-the-art of new fabrication techniques which are under development in recent years were analysed...}
place = {Korea, Republic of}
year = {1993}
month = {May}
}