Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient

References

• Sehgal BR. Nuclear safety in light water reactors severe accident phenomenology. USA: Academic Press; 2012.
   Google Scholar
• TEPCO HP [Internet]. [ cited 2020 Aug 18] Available from: https://www.tepco.co.jp/decommission/data/plant_data/ [in Japanese].
   Google Scholar
• Miwa S, Amaya M, Tanaka K, et al. Research program for the evaluation of fission product and actinide release behavior, focusing on their chemical forms -position and plan of the research program-, JAEA-review; 2013 [in Japanese].
   Google Scholar
• Tsurikov DF, Strizhov VF, Bechta SV, et al. Main results of the MASCA-1 and 2 projects. NEA/CSNI/R, vol 15 (2007), Russian Research Centre “KURCHATOV INSTITUTE” OECD MASCA Project; 2007.
   Google Scholar
• Fukasawa M, Tamura S. Thermodynamic analysis for molten corium stratification test MASCA with ionic liquid U-Zr-Fe-O-B-C-FPs database. J Nucl Sci Technol. 2007;44(9):1210–1219.
   Web of Science ®Google Scholar
• Journeau C, Piluso P, Correggio P, et al. The PLINIUS/Colima CA-U3 test on fission-product aerosol release over a VVER-type corium pool. Rapport CEA-R-6160; 2007.
   Google Scholar
• Kitagaki T, Ikeuchi H, Yano K, et al. Characterization of the VULCANO test products for fuel debris removal from the Fukushima Daiichi Nuclear Power Plant. Prog Nucl Energy. 2018;5:217–220.
   Google Scholar
• Kitagaki T, Yano K, Ogino H, et al. Thermodynamic evaluation of the solidification phase of molten Core-concrete under estimated Fukushima Daiichi nuclear power plant accident conditions. J Nucl Mater. 2017;486:206–215.
   Web of Science ®Google Scholar
• Brissonneau L, Ikeuchi H, Piluso P, et al. Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants. J Nucl Mater. 2020;528:151860_1-151860_18.
   Web of Science ®Google Scholar
• Nakayoshi A, Jegou C, Windt LD, et al. Leaching behavior of prototypical Corium samples; a step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors. Nucl Eng Des. 2020;36:110522_1-110522_18.
   Google Scholar
• Japan Atomic Energy Relations Organization HP [Internet]. [ cited 2020 Aug 18] Available from: https://www.jaero.or.jp/data/03syuppan/energy_zumen/energy_zumen.html (in Japanese).
   Google Scholar
• Arvanitidis I, Sichen D, Seetharaman SA. Study of the thermal decomposition of BaCO3. Metall Mater Trans B. 1996;27:409–416.
   Web of Science ®Google Scholar
• Bagherisereshki E, Tran J, Lei F, et al. Investigation into SrO/SrCO3 for high temperature thermochemical energy storage. Sol Energy. 2018;160:85–93.
   Web of Science ®Google Scholar
• Ball RGJ, Mignanelli MA, Barry TI, et al. The calculation of phase equilibria of oxide core-concrete systems. J Nucl Mater. 1993;201:238–249.
   Web of Science ®Google Scholar
• Suzuki M, Sodeoka S, Inoue T. Structure control of plasma sprayed zircon coating by substrate preheating and post heat treatment. Mater Trans. 2005;46(3):669–674.
   Web of Science ®Google Scholar
• Ota R, Kuribayashi H, Fukunaga J. Viscosity and crystallization behavior of non-alkali multicomponent glass. J Soc Mater SciJap. 1991;40(451):395–399. [in Japanese].
   Google Scholar
• Imaoka M, Yamazaki T. Studies of the glass-formation range of silicate systems. investigations on the glass-formation range, 2. J Ceram Assoc Japan 1963;71(816):215–223 [in Japanese].
   Google Scholar
• Koizumi S, Xu G, Ueda S, et al. Dissolution behavior of Fe from CaO-SiO2-FeOx glassy phase. Tetsu-to-Hagané. 2019;105(6):664–673. [in Japanese].
   Web of Science ®Google Scholar
• Wang JS, Shen FH. The development of SiO2 resistant Cr-doped glass ceramics for high Cr4+emission. J Non Cryst Solids. 2012;358(2):15:246–251.
   Web of Science ®Google Scholar
• Takano M. Characterization study on fuel debris. Atomic Energy Society of Japan 2016 Fall Meeting; 2016 July 6. Available from: http://www.aesj.or.jp/~wchem/27-5kennkyukai.pdf [in Japanese].
   Google Scholar
• Wang D, Su D, Schlögl R. Crystallographic shear defect in molybdenum oxides: structure and TEM of molybdenum sub‐oxides Mo18O52 and Mo8O23. Cryst Res Technol. 2003;38(2):153–159.
   Web of Science ®Google Scholar
• Ishikawa S, Matsuo T, Takeyama M. Phase equilibria among γ-Fe, γ-Fe and Fe2Mo phases and stability of the laves phase in Fe-Mo-Ni ternary system at elevated temperatures. Mrs Proc. 2006;0980-II05-17.
   Google Scholar
• Takano M, Nishi T, Shirasu N. Characterization of solidified melt among materials of UO2 fuel and B4C control blade. J Nucl Sci Technol. 2014;51:859–875.
   Web of Science ®Google Scholar
• Barin I. Thermochemical data of pure substances. 3rd ed. Germany: Wiley-VCH; 1995.
   Google Scholar
• Lindemer TB, Besmann TM. Chemical thermodynamic representation of <UO2±x>. J Nucl Mater. 1985;130:473–488.
   Web of Science ®Google Scholar
• Cheynet B, Fischer E. MEPHISTA: a thermodynamic database for new generation nuclear fuels. [ cited 2020 July 30] Available from: http://hal.archives-ouvertes.fr/hal-00222025/fr/
   Google Scholar
• Washiya T. Fundamental research program for removal of fuel debris. International Symposium on the Decommissioning of TEPCO’s Fukushima Daiichi Nuclear Power Plant Unit 1-4; Japan; 2017 Dec 12.
   Google Scholar
• Burakov BE, Anderson EB, Shabalev SI, et al. The behavior of nuclear fuel in first days of the chernobyl accident. Mrs Proc. 1996;465:1297–1308.
   Google Scholar