Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

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• 作者：Jaewoon Yoo ; ^{jwyoo@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Jinwook Chang ; Jae-Yong Lim ; Jin-Sik Cheon ; Tae-Ho Lee ; Sung Kyun Kim ; Kwi Lim Lee ; Hyung-Kook Joo
• 关键词：Inherent Safety ; Metal Fuel ; Passive Safety ; Pool Type ; Sodium Cooled Fast Reactor
• 刊名：Nuclear Engineering and Technology
• 出版年：2016
• 出版时间：October 2016
• 年：2016
• 卷：48
• 期：5
• 页码：1059-1070
• 全文大小：1955 K

文摘

The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.