2,279
Views
78
CrossRef citations to date
0
Altmetric
Article

A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention

, , , , , & show all
Pages 493-513 | Received 26 Aug 2013, Accepted 16 Dec 2013, Published online: 20 Jan 2014

References

  • Sagayama Y. Launch of fast reactor cycle technology development project in Japan. Paper presented at: Proc. Global 2007; 2007 Sep 9–13; Boise, ID. [CD-ROM].
  • Nakanishi S, Hosoya T, Kubo S, Kotake S, Takamatsu M, Aoyama T, Ikarimoto I, Kato J, Shimakawa Y, Harada K. Development of passive shutdown system for SFR. J Nucl Technol. 2010;170(1):181–188.
  • Ichimiya M, Mizuno T, Kotake S. A next generation sodium-cooled fast reactor concept and its R&D program. J Nucl Eng Technol. 2007;39(3):171–186.
  • Kotake, S, Sakamoto Y, Mihara T, Kubo S, Uto N, Kamishima Y, Aoto K, Toda M. Development of advanced loop-type fast reactor in Japan. J Nucl Technol. 2010;170(1):133–147.
  • Niwa H. Safety implications of the EAGLE experimental results for the FaCT project. Paper presented at: Proc. Int. Conf. Nuclear Power of Republic Kazakhstan; 2007 Sep 3–5; Kurchatov, Kazakhstan. [CD-ROM].
  • Konishi K, Kubo S, Sato I, Koyama K, Toyooka J, Kamiyama K, Kotake S, Vurim AD, Gaidaichuk VA, Pakhnits AV, Vassiliev YS. The EAGLE project to eliminate the recriticality issues of fast reactors – progress and results of in-pile tests. Paper presented at: Proc. NTHAS5; 2006 Nov 26–29; Jeju, Korea. [CD-ROM].
  • Sato I, Tobita Y, Konishi K, Kamiyama K, Toyooka J, Nakai R, Kubo S, Kotake S, Koyama K, Vassiliev Y, Vurim A, Zuev V, Kolodeshnikov A. Safety strategy of JSFR eliminating severe recriticality events and establishing in-vessel retention in the core disruptive accident. J Nucl Sci Technol. 2011;48(4):556–566.
  • Sato I, Yamano H, Tobita Y. Development of severe accident evaluation technology (level 2 PSA) for sodium-cooled fast reactors (2). Identification of dominant factors in initiating phase of unprotected events. Paper presented at: Proc. ICAPP’09; 2009 May 10–14; Tokyo, Japan. [CD-ROM].
  • Konishi K, Toyooka J, Kamiyama K, Sato I, Kubo S, Kotake S, Koyama K, Vurim AD, Gaidaichuk VA, Pakhnits AV, Vassiliev YS. The results of a wall failure in-pile experiment under the EAGLE project. Nucl Eng Des. 2007;237(22):2165–2174.
  • Sato I, Lemoine F, Struwe D. Transient fuel behavior and failure condition in the CABRI-2 experiments. Nucl Technol. 2004;145(1):115–137.
  • Onoda Y, Fukano Y, Sato I, Marquie C, Duc B. Three-pin cluster CABRI tests simulating the unprotected loss-of-flow accident in sodium-cooled fast reactors. J Nucl Sci Technol. 2011;48(2):188–204.
  • Rothman AB. TREAT experiments with irradiated fuel simulating hypothetical loss-of-flow accidents in large LMFBRs. Paper presented at: Proc. Int. Mtg. Fast Reactor Safety Technology; 1979 Aug 19–23; Seattle, WA. p. 924.
  • Bauer TH, Morman JA, Hill DJ, DeVolpi A, Goldman AJ. Post-failure material movement in the PFR/TREAT experiments. Paper presented at: Proc. Int. Mtg. Fast Reactor Safety and Related Physics; 1986 May 12–16; Guernsey, UK. p. 1647.
  • Kondo S, Morita K, Tobita Y, Shirakawa N. SIMMER-III: an advanced computer program for LMFBR severe accident analysis. Paper presented at: Proc. ANP’92; 1992 Oct 25–29; Tokyo, Japan. IV, p. 40.5-1.
  • Tobita Y, Kondo S, Yamano H, Morita K, Maschek W, Coste P, Cadiou T. The development of SIMMER-III, an advanced computer program for LMFR safety analysis and its application to sodium experiments. Nucl Technol. 2006;153(3):245–255.
  • Toyooka J, Endo H, Tobita Y, Ninikata H. A study on mechanism of early failure of inner duct wall within fuel subassembly with high heat flux from molten core materials based on analysis of an EAGLE experiment simulating core disruptive accidents in an LMFBR. Nihon-Genshiryoku-Gakkai Shi (J At Energy Soc Jpn). 2013;12(1):50–66. Japanese.
  • Kamiyama K, Tobita Y, Suzuki T, Matsuba K. Development of an assessment methodology for the molten-fuel discharge behavior in the core disruptive accident of sodium-cooled fast reactors. Paper presented at: Proc. ISSNP2013; 2013 Nov 22–24; Beijing, China.
  • Kamiyama K, Konishi K, Sato I, Toyooka J, Matsuba K, Zuyev V, Pakhnits A, Vurim A, Gaidaichuk V, Kolodeshnikov A, Vassiliev Y. Experimental studies on upward fuel discharge during core disruptive accident in sodium-cooled fast reactors. Paper presented at: Proc. NTHAS8; N8P1035; 2012 Dec 9–12; Beppu, Japan.
  • Petersen JF. TAC2D, a general purpose two-dimensional heat transfer computer code, user's manual: USAEC Report, GA-8868, Gulf General Atomic. San Francisco (CA): US Atomic Energy Commission; 1969.
  • Saito M, Sato K, Imahori S. Experimental study on penetration behaviors of water jet into freon-11 and liquid nitrogen. Paper presented at: Proc. ANS National Heat Trans. Conf.; 1988 Jul 24–27; Houston, TX. pp. 173–183.
  • Kondo Sa, Konishi K, Isozaki M, Imahori S, Furutani A, Brear DJ. Experimental study on simulated molten jet-coolant interaction. Nucl Eng Des. 1995;155(1–2):73–84.
  • Magallon D, Hohmann H, Schins H. Pouring of 100-kg-scale molten UO2 into sodium. Nucl Technol. 1992;98:79–90.
  • Matsuba K, Kamiyama K, Konishi K, Toyooka J, Sato I, Zuev V, Kolodeshnikov A, Vasilyev Y. Experimental study on material relocation during core disruptive accident in sodium-cooled fast reactors – results of a series of fragmentation tests for molten oxide discharged into a sodium pool. Paper presented at: Proc. NTHAS8, N8P1038, 2012 Dec 9–12; Beppu, Japan. [CD- ROM].
  • Lipinski RJ. A coolability model for post-accident nuclear reactor debris. Nucl Technol. 1984;65(1):53–66.
  • Mitchell GW, Ottinger CA, Meister H. The D10 experiment: coolability of UO2 debris in sodium with downward heat removal (NUREG/CR-4055 SAND84-1144 R7). Washington, DC: Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission; 1984.
  • Koyama K, Yamada Y, Hayakawa S, Watanabe M, Watanabe O. Development of severe accident evaluation technology (level 2 PSA) for sodium-cooled fast reactors (4). Identification of dominant factors in core material relocation and heat removal phases. Paper presented at: Proc. ICAPP’09; 2009 May 10–14; Tokyo, Japan. [CD-ROM].
  • Cheng S, Yamano H, Suzuki T, Tobita Y, Nakamura Y, Zhang B, Matsumoto T, Morita K. Characteristics of self-leveling behavior of debris beds in a series of experiments. Nucl Eng Technol. 2013;45:323–334.

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:

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:

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.