Advanced search
Publication Cover
Journal of Nuclear Science and Technology Volume 53, 2016 - Issue 3
Submit an article Journal homepage
928
Views
8
CrossRef citations to date
0
Altmetric
Article

Development of natural circulation analysis methods for a sodium cooled fast reactor

Kazuhiro OyamaMitsubishi FBR Systems (MFBR), Inc., 2-34-17 Jingumae, Shibuya-ku, Tokyo150-0001, JapanCorrespondence[email protected]
,
Junji EndoMitsubishi FBR Systems (MFBR), Inc., 2-34-17 Jingumae, Shibuya-ku, Tokyo150-0001, Japan
,
Norihiro DodaJapan Atomic Energy Agency (JAEA), O-arai Engineering Center, 4002 Narita, O-arai, Ibaraki311-1393, Japan
,
Ayako OnoJapan Atomic Energy Agency (JAEA), O-arai Engineering Center, 4002 Narita, O-arai, Ibaraki311-1393, Japan
,
Takahiro MurakamiCentral Research Institute of Electric Power Industry (CRIEPI), 1646 Abiko, Abiko-shi, Ibaraki270-1194, Japan
&
Osamu WatanabeMitsubishi FBR Systems (MFBR), Inc., 2-34-17 Jingumae, Shibuya-ku, Tokyo150-0001, Japan
Pages 353-370 | Received 02 Dec 2014, Accepted 22 Apr 2015, Published online: 16 Jun 2015

References

  • Kotake S, Sakamoto Y, Mihara T. Development of advanced loop-type fast reactor in Japan. J Nucl Sci Technol. 2010;170:133–147.
  • Sawada M, Arikawa H, Mizoo N. Experiment and analysis on natural convection characteristics in the experimental fast reactor Joyo. Nucl Eng Des. 1990;120:341–347.
  • Nishimura M, Kamide H, Hayashi K, et al. Transient experiments on fast reactor core thermal-hydraulics and its numerical analysis inter-subassembly heat transfer and inter-wrapper flow under natural circulation conditions. Nucl Eng Des. 2000;200:157–175.
  • Yamaguchi A, Oiwa A, Hasegawa T. Plant wide thermal hydraulic analysis of natural circulation test at Joyo with MK-II irradiation core. Proceedings of NURETH-4, Vol. 1; 1989 Oct 10–13; Karlsruhe, Germany.
  • Koga T, Murakami T, Eguchi Y, et al. Water test of natural circulation for decay heat removal in JSFR. Proceedings of NURETH-14; 2011 Sep 25–30; Toronto, Canada. No.172.
  • Kamide H, Kobayashi J, Ono A, et al. Sodium experiment on fully natural circulation systems for decay heat removal in Japan sodium-cooling fast reactor. Proceedings of NURETH-14; 2011 Sep 25–30; Toronto, Canada. No.179.
  • Tenchine D, Pialla D, Fanning TH, et al. International benchmark on the natural convection test in Phenix reactor. Nucl Eng Des. 2013;258:189–198.
  • Watanabe O, Oyama K, Endo J, et al. Development of evaluation methodology for natural circulation decay heat removal system in a sodium cooled fast reactor. J Nucl Sci Technol. 2015 (in printing).
  • Ohyama K, Watanabe O, Eguchi Y, et al. Decay heat removal system by natural circulation for JSFR. Proceedings of FR09; 2009 Dec 7–10; Kyoto, Japan.
  • Yamada F, Ohira H. Numerical simulation of Monju plant dynamics by super-COPD using previous startup tests data. Proceedings of ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting and 8th International Conference on Nanochannels, Microchannels and Minichannels, FEDSM-ICNMM2010-30287; 2010 Aug 1–5; Montreal, Canada.
  • Watanabe O, Kotake S, Kubo S. Study on natural circulation evaluation method for a large FBR. Proceedings of NURETH-8; 1997 Sep 30–Nov 4; Kyoto, Japan. No.12.
  • Ninokata H, Efthimiadis A, Todreas NE. Distributed resistance modeling of wire-wrapped rod bundles. Nucl Eng Des. 1987;104:93–102.
  • Yamada F, Fukano Y, Nishi H, et al. Development of natural circulation analytical model in super-COPD code and evaluation of core cooling capability in Monju during a station blackout. Am Nucl Soc. 2014;188:292–321.
  • STAR-CD, methodology, version 4.14. Computational Dynamics Limited; 2010.
  • Yakhot V, Orszag. Renormalization group analysis of turbulence – I: basic theory. J Sci Comput. 1986;1:1–51.
  • Yakhot V, Orszag SA, Thangam S, et al. Development of turbulence models for shear flows by a double expansion technique. Phys Fluids. 1992;A4(7):1510–1520.
  • Doda N, Oshima H, Kamide H, et al. Development of core hot spot evaluation method for a loop type fast reactor equipped with natural circulation decay heat removal system. J Nucl Sci Technol. ( under review).
  • Adams B, Ebeida M, Eldred M, et al. DAKOTA version 5.2 user's manual. Sandia National Laboratories; 2011.

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.