Development of advanced CANDU PHWR -Development of the advanced CANDU technology-
Creators
- Seok, Ho Cheon1
- Na, Yeong Hwan1
- Seok, Soo Dong1
- Lee, Bo Uk1
- Kwak, Ho Sang1
- Kim, Bong Ki1
- Kim, Seok Nam1
- Min, Byeong Joo1
- Park, Jong Ryunl1
- Shin, Jeong Cheol1
- Lee, Kyeong Ho1
- Lee, Dae Hee1
- Lee, Deuk Soo1
- Lee, Yeong Uk1
- Lee, Jeong Yang1
- Jwon, Jong Seon1
- Jwon, Chang Joon1
- Ji, Yong Kwan1
- Han, Ki Nam1
- Kim, Kang Soo1
- Kim, Dae Jin1
- Kim, Seon Cheol1
- Kim, Seong Hak1
- Kim, Yeon Seung1
- Kim, Yun Jae1
- Kim, Jeong Kyu1
- Kim, Jeong Taek1
- Kim, Hang Bae1
- Na, Bok Kyun1
- Namgung, In1
- Moon, Ki Hwan1
- Park, Keun Ok1
- Shon, Ki Chang1
- Song, In Ho1
- Shin, Ji Tae1
- Yeo, Ji Won1
- Oh, In Seok1
- Jang, Ik Ho1
- Jeong, Dae Won1
- Jeong, Yong Hwan1
- Ha, Jae Hong1
- Ha, Jeong Koo1
- Hong, Hyeong Pyo1
- Hwang, Jeong Ki .1
- Korea Cancer Center Hospital, Seoul (Korea, Republic of)
- 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Description
The target of this project is to assess the feasibility of improving PHWR and to establish the parameter of the improved concept and requirements for developing it. To set up the requirements for the Improved Pressurized Heavy Water Reactor: (1) Design requirements of PHWR main systems and Safety Design Regulatory Requirements for Safety Related System i.e. Reactor Shutdown System, Emergency Core Cooling System and Containment System were prepared. (2) Licensing Basis Documents were summarized and Safety Analysis Regulatory. Requirements were reviewed and analyzed. To estimate the feasibility of improving PHWR and to establish the main parameters of the concept of new PHWR in future: (1) technical level/developing trend of PHWR in Korea through Wolsong 2, 3 and 4 design experience and Technical Transfer Program was investigated to analyze the state of basic technology and PHWR improvement potential. (2) CANDU 6 design improvement tendency, CANDU 3 design concept and CANDU 9 development state in other country was analyzed. (3) design improvement items to apply to the reactors after Wolsong 2, 3 and 4 were selected and Plant Design Requirements and Conceptual Design Description were prepared and the viability of improved HWR was estimated by analyzing economics, performance and safety. (4) PHWR technology improving research and development plan was established and international joint study initiated for main design improvement items
Availability note (English)
MF available from INIS under the Report Number.Files
26011448.pdf
Files
(17.6 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 541 p.
- Report number
- KAERI/RR--1377/93
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 26011448
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; CANDU TYPE REACTORS; COST BENEFIT ANALYSIS; COST ESTIMATION; ENGINEERING DRAWINGS; LICENSING REGULATIONS; PHWR TYPE REACTORS; SAFETY STANDARDS
- Descriptors DEC
- DIAGRAMS; ECONOMIC ANALYSIS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; LAWS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; REGULATIONS; REMOVAL; STANDARDS; THERMAL REACTORS