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Journal Articles

Leaching behavior of prototypical Corium samples; A Step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors

Nakayoshi, Akira; Jegou, C.*; De Windt, L.*; Perrin, S.*; Washiya, Tadahiro

Nuclear Engineering and Design, 360, p.110522_1 - 110522_18, 2020/04

https://doi.org/10.1016/j.nucengdes.2020.110522

Times Cited Count：15 Percentile：87.35(Nuclear Science & Technology)

Journal Articles

Monte Carlo criticality analysis under material distribution uncertainty

Ueki, Taro

Journal of Nuclear Science and Technology, 54(3), p.267 - 279, 2017/03

https://doi.org/10.1080/00223131.2016.1260066

Times Cited Count：8 Percentile：60.93(Nuclear Science & Technology)

Analysis framework under material distribution uncertainty is investigated for the Monte Carlo (MC) criticality calculation of continuously mixed media formed via molten core concrete interaction. Deterministic trigonometric functions and randomized Weierstrass functions are utilized to represent the spatially continuous variation. Numerical results indicate that the effective multiplication factor (k $_{rm eff}$ ) under random spatial variation can depart significantly from the k $_{rm eff}$ of a reference uniform medium. It is also shown that the deterministic modeling provides an upper-bound measure for extreme results from random realizations.

Journal Articles

Analysis of WITCH/LINER experiments on heat transfer between gas-agitated steel melt and vertical wall

Maruyama, Yu; Sugimoto, Jun

Journal of Nuclear Science and Technology, 36(10), p.914 - 922, 1999/10

https://doi.org/10.3327/jnst.36.914

Times Cited Count：3 Percentile：28.69(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

CORCON-Mod3 analysis of SURC experiments on molten core concrete interaction

J.Yan*; Maruyama, Yu; Sugimoto, Jun

JAERI-Tech 95-052, 27 Pages, 1995/12

JAERI-Tech-95-052.pdf:1.32MB

no abstracts in English

Oral presentation

Phases and morphology in the simulated MCCI products prepared by arc melting method

Takano, Masahide; Onozawa, Atsushi; Sudo, Ayako

no journal, ,

To understand the characteristics of MCCI products in Fukushima Daiichi Nuclear Power Station, the simulated MCCI products in laboratory scale were prepared by arc melting of compacted powder mixtures of core materials and concrete. Stainless steel, boron carbide, metallic zirconium, (U,Zr)O $_{2}$ , GdO $_{1.5}$ , and platinum group elements were selected as the core materials. Phases, morphology, and micro hardness were analyzed on cross-section of the solidified specimens. The specimens consisted of oxide part (MO $_{2}$ corium and silicate glass or Al-Ca-O) and metallic part (alloys and borides). The phase relationships in the MCCI products were found to be dominated by the initial concrete/Zr mixing ratio, because the dehydration of concrete is the main oxidation factor and the metallic zirconium acts as a strong reductant. Micro hardness of main phases are 7 GPa for silicate glass, 13-15 GPa for (U,Zr,Gd,Ca)O $_{2}$ corium, and 25 GPa for ZrB $_{2}$ and ferrous borides, respectively.