Numerical analysis of the Sodium–Water Reaction in a minichannel to evaluate the safety of a Printed Circuit Steam Generator-Reference-Cited by-同舟云学术

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Numerical analysis of the Sodium–Water Reaction in a minichannel to evaluate the safety of a Printed Circuit Steam Generator

Published:2022-03-10 Issue:6 Volume:59 Page:688-708
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kim Taewoo¹²,Kim Sang Ji²

Affiliation:

1. Advanced Nuclear System Engineering, Korea University of Science and Technology, Daejeon, Republic of Korea

2. Versatile Reactor Technology Development Division, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea

Funder

National Research Foundation of Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2021.2003882

Reference42 articles.

1. Steam Generator Vessel Pressures Resulting from a Sodium-Water Reaction—A Computer Analysis with the SWEAR Code

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

3. An experimental study on impingement wastage of Mod 9Cr 1Mo steel due to sodium water reaction

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