225
Views
0
CrossRef citations to date
0
Altmetric
Article

Influences of the ZrC coating process and heat treatment on ZrC-coated kernels used as fuel in Pu-burner high temperature gas-cooled reactor in Japan

, , , , , & show all
Pages 107-116 | Received 13 Apr 2020, Accepted 03 Aug 2020, Published online: 23 Aug 2020

References

  • What is HTGR? [Internet]. Japan: Japan Atomic Energy Agency; [ cited 2020 Apr. 7]. Available from: https://www.jaea.go.jp/04/o-arai/nhc/en/data/data_01.html
  • Fukuda K, Ogawa T, Hayashi K, et al. Research and development of HTTR coated particle fuel. J Nucl Sci Technol. 1991;28:570–581.
  • Aihara J, Goto M, Ueta S, et al. Code-B-2.5.2 for stress calculation for SiC-TRISO fuel particle. Tokai-mura (Japan): Japan Atomic Energy Agency; 2020. (JAEA-Data/Code 2019–018) [in Japanese].
  • Aihara J, Ueta S, Honda M, et al. Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan. J Nucl Mater. 2019;522:32–40.
  • Ueta S, Aihara J, Sakaba N, et al. Fuel performance under continuous high temperature operation of the HTTR. J Nucl Sci Tech. 2014;51:1345–1354.
  • Saito S, Tanaka T, Sudo Y, et al. Design of high temperature engineering test reactor (HTTR). Japan: Japan atomic energy agency. Japan Atomic Energy Research Institute, 1994 Sep.; 1994.
  • Fujikawa S, Okubo M, Nakazawa T, et al. Rise-to-power test of the HTTR (high temperature engineering test reactor). Nihon-Genshiryoku-Gakkai-Wabun-Ronbun-Shi (J. At. Energy Soc. Jpn.). 2002 Dec; 1:361–372. [in Japanese].
  • Fujikawa S, Hayashi H, Nakazawa T, et al. Achievement of reactor-outlet coolant temperature of 950C in HTTR. J Nucl Sci Technol. 2004 Dec;41:1245–1254.
  • Ueta S, Sawa AJ, Yasuda K, et al. Development of high temperature gas-cooled reactor (HTGR) fuel in Japan. Prog Nucl Energy. 2011 Sep;53:788–793.
  • The federation of electric power companies of Japan, Plans for the utilization of plutonium to be recovered at the Rokkasho reprocessing plant (RRP) FY2010 [Internet]. Japan: The Federation of Electric Power Companies of Japan; 2010 Sep. 17 [cited 2020 Apr 7]. Available from: http://www.fepc.or.jp/english/news/plans/__icsFiles/afieldfile/2010/09/17/plu_keikkei_E_1.pdf
  • Plutonium utilization in Japan [Internet]. Japan: Japan Atomic Energy Commission; 2017 Oct [cited 2020 Apr 7]. Available from: http://www.aec.go.jp/jicst/NC/about/kettei/kettei171003_e.pdf
  • The status report of plutonium management in Japan −2018- [Internet]. Japan: Cabinet Office of Japan; 2019 July 30 [cited 2020 Apr 7]. Available from: http://www.aec.go.jp/jicst/NC/iinkai/teirei/3-3set_20190730.pdf#search=%27The+Status+Report+of+Plutonium+Management+in+Japan%27
  • Fukaya Y, Goto M, Ohashi H, et al. Proposal of a plutonium burner system based on HTGR with high proliferation resistance. J Nucl Sci Technol. 2014;51:818–831.
  • Goto M, Demachi K, Ueta S, et al. Conceptual study of a plutonium burner high temperature gas-cooled reactor with high nuclear proliferation resistance; Proceedings of GLOBAL 15; 2015 Sep 20–24; Paris, France.
  • Ueta S, Mizuta N, Fulaya Y, et al. Study on plutonium burner high temperature gas-cooled reactor in Japan –Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel. Nucl Eng Des. 2020;357:110419.
  • Ueta S, Aihara J, Yasuda A, et al. Fabrication of uniform ZrC coating layer for the very high temperature reactor fuel. J Nucl Mater. 2008;376:146–151.
  • Honda M, Saiki Y, Takahashi M, et al. Study on Pu-burner high temperature gas-cooled reactor in Japan (4) 3S-TRISO fuel fabrication, Proceedings of HTR 2018; 2018 Oct 8–10;Warsaw, Poland.
  • H S K, C Y J, B H L, et al. Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development. J Nucl Mater. 2008;378:98–104.
  • Dörr W, Hellmann S, Mages G. Study of formation of UO2-PuO2 solid solution by means of UO2-CeO2 simulate. J Nucl Mater. 1986;140:7–10.
  • Y W L, H S K, S H K, et al. Preparation of simulated inert matrix fuel with different powders by dry milling method. J Nucl Mater. 1999;274:7–14.
  • Zimmer E, Ganguly C, Borchardt J, et al. SGMP – an advanced method for fabrication of UO2 and mox fuel pellet. J Nucl Mater. 1988;152:169–177.
  • Ueta S, Aihara J, Goto M, et al. Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating. Mech Eng J. 2018;5:18–00084.
  • Aihara J, Ueta S, Yasuda A, et al. TEM/STEM observation of ZrC-coating layer for advanced high-temperature gas-cooled reactor fuel. J Am Ceram Soc. 2007;90:3968–3972.
  • Aihara J, Ueta S, Yasuda A, et al. TEM/STEM observation of ZrC coating layer for advanced high-temperature gas-cooled reactor fuel, part II. J. Am Ceram Soc. 2009;92:197–203.
  • Aihara J, Ueta S, Yasuda A, et al. Effect of heat treatment on TEM microstructures of zirconium carbide layer in fuel particle for advanced high temperature gas cooled reactor. Mater. Trans. 2009;50:2631–2636.
  • Aihara J, Maekawa M, Ueta S, et al. Microstructures and positron annihilation spectroscopy of nearly stoichiometric ZrC coating layers for advanced high-temperature gas-cooled reactor fuel. J Am Ceram Soc. 2011;94:4519–4522.
  • Ueta S, Aihara J, Yasuda A, et al. Development on fabrication and inspection techniques for the ZrC-coated fuel particle as an advanced high temperature gas cooled reactor fuel. Hyomen. 2008;46:222–232. [in Japanese]
  • Brambilla G, Gerontopulos P, Neri D. The SNAM process for the preparation of ceramic nuclear fuel microspheres: laboratory studies. Energia Nucleare. 1970;17:217–224.
  • Ogawa T, Ikawa K, Iwamoto K. Microhardness and microstructure of chemically vapor deposited ZrC-C alloy. J Nucl Mater. 1976;62:322–324.
  • Ogawa T, Ikawa K, Iwamoto K. Chemical vapor deposition of ZrC within a spouted bed by bromide process. J Nucl Mater. 1981;97:104–112.
  • Yasuda A, Ueta S, Aihara J, et al. Development of production technology of ZrC-coated particle (No.1) (Contract Research). Tokai-mura (Japan): Japan Atomic Energy Agency; 2008. (JAEA-Technology 2008-073) [in Japanese].
  • Sawa K, Ueta S, Aihara J, et al. Development of ceramics-coated particle fuel for very high-temperature gas-cooled reactors. Nihon-Genshiryoku-Gakkai-Wabun-Ronbun-Shi (J. At. Energy Soc. Jpn.). 2007;6:113–325. [in Japanese].

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.