A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
- Lee, Kwi Lim
- Ha, Kwi-Seok
- Jeong, Jae-Ho
- Choi, Chi-Woong
- Jeong, Taekyeong
- Ahn, Sang June
- Lee, Seung Won
- Chang, Won-Pyo
- Kang, Seok Hun
- Yoo, Jaewoon
Publication date
October 2016
DOI Publisher
, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society.Abstract
AbstractKorea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and the subchannel blockage events are analyzed with MATRA-LMR-FB. In addition, the in-vessel source term is calculated based on the super-safe, small, and simple reactor methodology. The results show that the PGSFR meets safety acceptance criteria with a sufficient margin during the events and keeps accidents from deteriorating into more severe accidents
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