Design and analysis of CANDU advanced fuel -Development of the advanced CANDU technology-
Creators
- Seok, Ho Cheon1
- Shim, Ki Seop1
- Byeon, Taek Sang1
- Park, Kwang Seok1
- Kim, Bong Ki1
- Lee, Yeong Uk1
- Jeong, Chang Joon1
- Oh, Deok Joo1
- Lee, Ui Joo1
- Park, Joo Hwan1
- Lee, Sang Yong1
- Jeong, Beop Dong1
- Choi, Han Rim1
- Lee, Yeong Jin1
- Choi, Cheol Jin1
- Choi, Jong Ho1
- Lee, Kwang Won1
- Cho, Cheon Hyi1
- On, Myeong Ryong1
- Kim, Taek Mo1
- Lim, Hong Sik1
- Lee, Kang Moon1
- Lee, Nam Ho1
- Lee, Kyu Hyeong .1
- Korea Cancer Center Hospital, Seoul (Korea, Republic of)
- 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Description
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
Availability note (English)
MF available from INIS under the Report Number.Files
26011443.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 347 p.
- Report number
- KAERI/RR--1317/93
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 26011443
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; DESIGN; FUEL ASSEMBLIES; INTERNATIONAL COOPERATION; KAERI; SAFETY ANALYSIS
- Descriptors DEC
- CANADIAN ORGANIZATIONS; COOPERATION; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS