Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical characteristics that allow it to violently react with ma...

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Bibliographic Details
Main Authors: Sang June Ahn, Kwi-Seok Ha, Won-Pyo Chang, Seok Hun Kang, Kwi Lim Lee, Chi-Woong Choi, Seung Won Lee, Jin Yoo, Jae-Ho Jeong, Taekyeong Jeong
Format: Article
Language:English
Published: Elsevier 2016-08-01
Series:Nuclear Engineering and Technology
Subjects:
Multidimensional Analysis of Reactor Safety-Liquid Metal Reactor
Prototype Generation IV Sodium-Cooled Fast Reactor
Sodium–Water Advanced Analysis Method-II
Sodium–Water Reaction
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573316000784

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http://www.sciencedirect.com/science/article/pii/S1738573316000784

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