Conceptual design of a copper-bonded steam generator for SFR and the development of its thermal-hydraulic analyzing code-Reference-Cited by-同舟云学术

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Conceptual design of a copper-bonded steam generator for SFR and the development of its thermal-hydraulic analyzing code

Published:2021-12 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Im Sunghyuk^ORCID,Jung Yohan,Hong Jonggan,Choi Sun Rock

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. Generation IV International Forum: a decade of progress through international cooperation;Kelly;Prog. Nucl. Energy,2014

2. A summary of sodium-cooled fast reactor development;Aoto;Prog. Nucl. Energy,2014

3. Evaluation of a sodium–water reaction event caused by steam generator tubes break in the prototype generation IV sodium-cooled fast reactor;Ahn;Nucl. Eng. Technol.,2016

4. Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea;Yoo;Nucl. Eng. Technol.,2016

5. Technology status of sodium-water reaction minimized heat exchanger;Hong,2018

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