A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

Korea 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 exten...

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Bibliographic Details
Main Authors: Kwi Lim Lee, Kwi-Seok Ha, Jae-Ho Jeong, Chi-Woong Choi, Taekyeong Jeong, Sang June Ahn, Seung Won Lee, Won-Pyo Chang, Seok Hun Kang, Jaewoon Yoo
Format: Article
Language:English
Published: Elsevier 2016-10-01
Series:Nuclear Engineering and Technology
Subjects:
Anticipated Transient Without Scram
Design Basis Accidents
Design Extended Conditions
MARS-LMR
MATRA-LMR-FB
Prototype Gen-IV Sodium-Cooled Fast Reactor
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Online Access:http://www.sciencedirect.com/science/article/pii/S1738573316301334

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http://www.sciencedirect.com/science/article/pii/S1738573316301334

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