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Kato, Masato; Oki, Takumi; Watanabe, Masashi; Hirooka, Shun; Vauchy, R.; Ozawa, Takayuki; Uwaba, Tomoyuki; Ikusawa, Yoshihisa; Nakamura, Hiroki; Machida, Masahiko
Journal of the American Ceramic Society, 107(5), p.2998 - 3011, 2024/05
Times Cited Count：0 Percentile：0.01(Materials Science, Ceramics)Takai, Toshihide; Furukawa, Tomohiro; Yamano, Hidemasa
Mechanical Engineering Journal (Internet), 8(4), p.20-00540_1 - 20-00540_11, 2021/08
In a core disruptive accident scenario, boron carbide, which is used as a control rod material, may melt below the melting temperature of stainless steel owing to the eutectic reaction with them. The eutectic mixture produced is assumed to extensively relocate in the degraded core, and this behavior plays an important role in significantly reducing the neutronic reactivity. However, these behaviors have never been simulated in previous severe accident analysis. To contribute to the improvement of the core disruptive accident analysis code, the thermophysical properties of the eutectic mixture in the solid state were measured, and regression equations that show the temperature (and boron carbide concentration) dependence are created.
Kaneko, Tetsuji; Tsukatani, Ichiro; Kiuchi, Kiyoshi
JAERI-Research 2005-005, 23 Pages, 2005/03
JAERI-Research-2005-005.pdf:1.65MB
Fuel elements used in The Reduced-Moderation Water Reactor (RMWR) have the lamellar structure consisting of MOX pellets and UO
blankets in order to attain the high breeding ratio and high burn-up simultaneously. It is a characteristic of the fuel elements that there is high thermal stress caused by inhomogeneous linear power density along the longitudinal direction of the fuel rod. Therefore, it is important to evaluate the local deformation behavior due to the transient temperature distribution. To estimate the thermal deformation behavior, the temperature and stress distribution of the fuel cladding tube assumed in the designed reactor were analyzed. Moreover, basic physical properties and mechanical properties for analyzing the deformation behavior were obtained by experiment using fuel cladding tubes made of candidate alloys. In addition, the appropriate experimental conditions for realizing the practical thermal deformation behavior of the fuel cladding tube was selected by adjusting the testing temperature distribution based on data obtained with thermal analysis.
pelletHarada, Katsuya; Nakata, Masahito; Yasuda, Ryo; Nishino, Yasuharu; Amano, Hidetoshi
HPR-356, 11 Pages, 2001/00
no abstracts in English
; *; *; Furukawa, Kazuo
J.Phys.,E, 10(9), p.921 - 927, 1977/00
no abstracts in English
; *; *; Furukawa, Kazuo
J.Phys.,E, 8(6), p.461 - 464, 1975/06
no abstracts in English
; *; Takehisa, Masaaki
JAERI-M 5495, 70 Pages, 1974/01
no abstracts in English
Tsuchimochi, Ryota; Kato, Masato; Hirooka, Shun; Matsumoto, Taku; White, J.*; McClellan, K.*
no journal, ,
High temperature XRD, Thermal expansion measurement, sound speeds measurement and DSC measurement of CaF were carried out. We confirmed that the specific heat of CaF explicity shows the effect of Frenkel defect formation on top of the heat capacity at constant volume and dilatational term. The analysis of the specific heat will be discussed together with the measured data.
