Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor-Reference-Cited by-同舟云学术

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

Published:2016-08 Issue:4 Volume:48 Page:952-964
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Ahn Sang June,Ha Kwi-Seok,Chang Won-Pyo,Kang Seok Hun,Lee Kwi Lim,Choi Chi-Woong,Lee Seung Won,Yoo Jin,Jeong Jae-Ho,Jeong Taekyeong

Funder

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. Sodium-water reaction phenomena associated with small leaks in LMFBR steam generator;Greene,1984

2. Liquid Metal Cooled Reactors: Experience in Design and Operation;International Atomic Energy Agency,2007

3. Interim Progress Report: Steam Generator Leak Detection System;Chien,2013

4. Development of Technical Basis for Leak-Before-Break Evaluation Procedures;Scott,2002

5. Large Sodium-Water Reaction: Preliminary Safety Analysis Report;Clinch River Breeder Reactor Project,1975

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1. An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR;Nuclear Science and Engineering;2023-06-09

2. Minor Actinides Transmutation and 233U Breeding in a Closed Th-U Cycle Based on Molten Chloride Salt Fast Reactor;Energies;2022-12-14

3. An analysis of the pressure wave propagation by the sodium-water reaction in the printed circuit steam generator using the SWAAM-II code;Annals of Nuclear Energy;2022-12

4. Numerical analysis of the Sodium–Water Reaction in a minichannel to evaluate the safety of a Printed Circuit Steam Generator;Journal of Nuclear Science and Technology;2022-03-10

5. Investigation into steam generator tube life expectancy affected by SFR transients;Progress in Nuclear Energy;2022-01

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