Advanced search
Publication Cover
Journal of Nuclear Science and Technology Volume 57, 2020 - Issue 8
Submit an article Journal homepage
514
Views
5
CrossRef citations to date
0
Altmetric
Article

Development of critical heat flux correlation for In-vessel retention

Chikako Iwakia Energy Systems Research and Development Center, Toshiba Energy Systems & Solutions Corporation, Isogo-ku, Yokohama, JapanCorrespondence[email protected]
,
Hisaki Satob Isogo Engineering Center, Toshiba Energy Systems & Solutions Corporation, Fukui, Isogo-ku, Yokohama, Japan
&
Daisuke Kanamoric Ohi Nuclear Power Station, The Kansai Electric Power Co., Inc., Fukui, Japan
Pages 951-962 | Received 02 Oct 2019, Accepted 03 Mar 2020, Published online: 19 Mar 2020

Citations (5)

Keep up to date with the latest research on this topic with citation updates for this article.

Subscribe to citation updates

Read on this site (1)

Chikako Iwaki, Hisaki Sato & Daisuke Kanamori. (2022) Evaluation of nanofluids for enhancing critical heat flux for in-vessel retention during sever reactor accidents. Journal of Nuclear Science and Technology 59:4, pages 499-509.
Read now

Articles from other publishers (4)

Yeon-Gun Lee & Il Woong Park. (2023) Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code. International Journal of Energy Research 2023, pages 1-17.
Crossref
Songyang Wang, Liu Yang, Zixiang Su, Jianzhong Song, Shenghui Liu & Xiaoke Li. (2023) Research progress on boiling heat transfer of nanofluids with emphasis on IVR-ERVC strategy. Thermal Science and Engineering Progress 39, pages 101716.
Crossref
Chiaki Kino & Kenichi Tezuka. (2023) Japanese research activity for offshore Floating Nuclear Power Plant国内における浮体式原子力発電の検討状況. Journal of the Atomic Energy Society of Japan 65:8, pages 489-493.
Crossref
Min Seop Song, Il Woong Park, Eung Soo Kim & Yeon-Gun Lee. (2022) Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate. Nuclear Engineering and Technology 54:1, pages 72-83.
Crossref

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.