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Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-

Technical Report:

Abstract

It has been projected that a total of 5 pressurized heavy water reactors (PHWR) including Wolsong 1 under operation and Wolsong 2, 3 and 4 under construction will be operated by 2006, and so about 500 ton of natural uranium will be consumed every year and a lot of spent fuels will be generated. Therefore, the ultimate goal of this R and D project is to develop the CANDU advanced fuel having the following capabilities compared with existing standard fuel: (1) To reduce linear heat generation rating by more than 15% (i.e., less than 50 kW/m), (2) To extend fuel burnup by more than 3 times (i.e., higher than 21,000 MWD/MTU), and (3) To increase critical channel power by more than 5%. In accordance, the followings are performed in this fiscal year: (1) Undertake CANFLEX-NU design and thermalmechanical performance analysis, and prepare design documents, (2) Establish reactor physics analysis code system, and investigate the compativility of the CANFLEX-NU fuel with the standard 37-element fuel in the CANDU-6 reactor. (3) Establish safety analysis methodology with the assumption of the CANFLEX-NU loaded CANDU-6 reactor, and perform the preliminary thermalhydraulic and fuel behavior for the selected DBA accidents, (4) Investigate reactor physics analysis  More>>
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1317/93
Reference Number:
SCA: 210400; 220300; PA: AIX-26:011443; EDB-95:028280; SN: 95001324177
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; CANDU TYPE REACTORS; FUEL ASSEMBLIES; ATOMIC ENERGY OF CANADA LTD; DESIGN; INTERNATIONAL COOPERATION; KAERI; SAFETY; 210400; 220300; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED; FUEL ELEMENTS
OSTI ID:
10111602
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612924; TRN: KR9400155011443
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
347 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Seok, Ho Cheon, Shim, Ki Seop, Byeon, Taek Sang, Park, Kwang Seok, Kim, Bong Ki, Lee, Yeong Uk, Jeong, Chang Joon, Oh, Deok Joo, Lee, Ui Joo, Park, Joo Hwan, Lee, Sang Yong, Jeong, Beop Dong, Choi, Han Rim, Lee, Yeong Jin, Choi, Cheol Jin, Choi, Jong Ho, Lee, Kwang Won, Cho, Cheon Hyi, On, Myeong Ryong, Kim, Taek Mo, Lim, Hong Sik, Lee, Kang Moon, Lee, Nam Ho, and Lee, Kyu Hyeong. Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-. Korea, Republic of: N. p., 1994. Web.
Seok, Ho Cheon, Shim, Ki Seop, Byeon, Taek Sang, Park, Kwang Seok, Kim, Bong Ki, Lee, Yeong Uk, Jeong, Chang Joon, Oh, Deok Joo, Lee, Ui Joo, Park, Joo Hwan, Lee, Sang Yong, Jeong, Beop Dong, Choi, Han Rim, Lee, Yeong Jin, Choi, Cheol Jin, Choi, Jong Ho, Lee, Kwang Won, Cho, Cheon Hyi, On, Myeong Ryong, Kim, Taek Mo, Lim, Hong Sik, Lee, Kang Moon, Lee, Nam Ho, & Lee, Kyu Hyeong. Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-. Korea, Republic of.
Seok, Ho Cheon, Shim, Ki Seop, Byeon, Taek Sang, Park, Kwang Seok, Kim, Bong Ki, Lee, Yeong Uk, Jeong, Chang Joon, Oh, Deok Joo, Lee, Ui Joo, Park, Joo Hwan, Lee, Sang Yong, Jeong, Beop Dong, Choi, Han Rim, Lee, Yeong Jin, Choi, Cheol Jin, Choi, Jong Ho, Lee, Kwang Won, Cho, Cheon Hyi, On, Myeong Ryong, Kim, Taek Mo, Lim, Hong Sik, Lee, Kang Moon, Lee, Nam Ho, and Lee, Kyu Hyeong. 1994. "Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-." Korea, Republic of.
@misc{etde_10111602,
title = {Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-}
author = {Seok, Ho Cheon, Shim, Ki Seop, Byeon, Taek Sang, Park, Kwang Seok, Kim, Bong Ki, Lee, Yeong Uk, Jeong, Chang Joon, Oh, Deok Joo, Lee, Ui Joo, Park, Joo Hwan, Lee, Sang Yong, Jeong, Beop Dong, Choi, Han Rim, Lee, Yeong Jin, Choi, Cheol Jin, Choi, Jong Ho, Lee, Kwang Won, Cho, Cheon Hyi, On, Myeong Ryong, Kim, Taek Mo, Lim, Hong Sik, Lee, Kang Moon, Lee, Nam Ho, and Lee, Kyu Hyeong}
abstractNote = {It has been projected that a total of 5 pressurized heavy water reactors (PHWR) including Wolsong 1 under operation and Wolsong 2, 3 and 4 under construction will be operated by 2006, and so about 500 ton of natural uranium will be consumed every year and a lot of spent fuels will be generated. Therefore, the ultimate goal of this R and D project is to develop the CANDU advanced fuel having the following capabilities compared with existing standard fuel: (1) To reduce linear heat generation rating by more than 15% (i.e., less than 50 kW/m), (2) To extend fuel burnup by more than 3 times (i.e., higher than 21,000 MWD/MTU), and (3) To increase critical channel power by more than 5%. In accordance, the followings are performed in this fiscal year: (1) Undertake CANFLEX-NU design and thermalmechanical performance analysis, and prepare design documents, (2) Establish reactor physics analysis code system, and investigate the compativility of the CANFLEX-NU fuel with the standard 37-element fuel in the CANDU-6 reactor. (3) Establish safety analysis methodology with the assumption of the CANFLEX-NU loaded CANDU-6 reactor, and perform the preliminary thermalhydraulic and fuel behavior for the selected DBA accidents, (4) Investigate reactor physics analysis code system as pre-study for CANFLEX-SEU loaded reactors.}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}