Critical flow prediction by system codes – Recent analyses made within the FONESYS network-Reference-Cited by-同舟云学术

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

Published:2020-09 Issue: Volume:366 Page:110731
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lanfredini M.,Bestion D.,D'Auria F.,Aksan N.^ORCID,Fillion P.,Gaillard P.,Heo J.,Karppinen I.,Kim K.D.,Kurki J.,Liu L.,Shen A.,Vacher J.-L.,Wang D.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference41 articles.

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3. Aksan, N., D’Auria, F., 1996. Status Report on Relevant Thermal hydraulic Aspects of Advanced Reactor Design, OECD/NEA, Report NEA/CSNI/R(96)22, Paris, France.

4. Aksan, N., Bestion, D., D’Auria, F., Hassan, Y., Lanfredini, M., Lutsanych, S., Moretti, F., Vaghetto, R., 2018. “Prospective For Nuclear Thermal Hydraulic Created By Ongoing And New Networks,” Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18.

5. Experimental study of the critical flashing flow through a relief line: evidence of the double-choked flow phenomenon;Attou;Int. J. Multiphase Flow,2000

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