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TiO
added with TiOHoshino, Tsuyoshi; Kobayashi, Takeshi*; Nashimoto, Makoto*; Kawamura, Hiroshi; Dokiya, Masayuki*; Terai, Takayuki*; Yamawaki, Michio*; Takahashi, Yoichi*
JAERI-Conf 2004-012, p.140 - 147, 2004/07
no abstracts in English
Yamanaka, Shinsuke*; Uno, Masayoshi*; Kurosaki, Ken*; ; Namekawa, Takashi
JNC TY9400 2000-011, 41 Pages, 2000/03
JNC-TY9400-2000-011.pdf:1.28MB
no abstracts in English
Harada, Katsuya; Nishino, Yasuharu; Mita, Naoaki; Amano, Hidetoshi
JAERI-Tech 2000-031, p.27 - 0, 2000/03
JAERI-Tech-2000-031.pdf:2.95MB
no abstracts in English
Kodaira, Tsuneo; Sukegawa, T.; Amano, Hidetoshi; Kanaitsuka, Fumio;
JAERI-Conf 99-009, p.20 - 31, 1999/09
no abstracts in English
Morita, Koji; Tobita, Yoshiharu; kondo, Satoru; E.A.Fischer*
JNC TN9400 2000-004, 38 Pages, 1999/05
JNC-TN9400-2000-004.pdf:1.11MB
An analytic thermophysical property model using general function forms is developed for a reactor safety analysis code, SIMMER-III. The function forms arc designed to represent correct behavior of properties of reactor-core materials over wide temperature ranges, especially for the thermal conductivity and the viscosity near the critical point. The most up-to-date and reliable sources for uranium dioxide, mixed-oxide fuel, stainless stee1, and sodium available at present are used to determine parameters in the proposed functions. This model is also designed to be consistent with a SIMMER-III model on thermodynamic properties and equations of state for reactor-corc materials.
Takeda, Tetsuaki; B.Han*; Ogawa, Masuro
JAERI-M 92-131, 125 Pages, 1992/09
no abstracts in English
; Iwamoto, K.; Ikawa, Katsuichi;
JAERI-M 84-236, 51 Pages, 1985/01
no abstracts in English
; Iwamoto, K.; Ikawa, Katsuichi
JAERI-M 82-134, 25 Pages, 1982/10
no abstracts in English
*; Kuriyama, Isamu
Polymer, 23, p.1377 - 1380, 1982/00
Times Cited Count：4 Percentile：30.9(Polymer Science)no abstracts in English
Higashi, Hideo*; Fukuyama, Hiroyuki*; Nishi, Tsuyoshi*; Yamano, Hidemasa
no journal, ,
Thermophysical properties of molten stainless steel (SUS316) are necessary to understand a core degradation mechanism in severe accidents of nuclear reactors. In this study, the normal spectral emissivity, heat capacity and thermal conductivity of liquid SUS316 were measured using an electromagnetic levitation technique in a dc magnetic field. The normal spectral emissivity has a negative wavelength dependence, and a negligible temperature dependence. The heat capacity and thermal conductivity of liquid SUS316 were measured using the noncontact laser modulation calorimetry. The heat capacity presents a constant value at a temperature range from 1661 to 1778 K. The thermal conductivity has a positive temperature dependence.
Takaki, Seiya; Takano, Masahide
no journal, ,
Nitride fuel with ZrN matrix have been studied for transmutation of minor actinide (MA). These are supposed to be designed as ZrN solid solution or TiN compounds with MA nitride from 20mol% to 40mol%. From the above, composition and temperature dependence of thermal conductivity for safety evaluation of the fuel have been studied with a little of MA. In the present study, we are aimed to clarify composition and temperature dependence of thermal conductivity of Dy
Zr
N solid solution as surrogate nitride fuel with MA in order to understand the dependence of the MA nitride fuel physically. In addition to, we introduce studies about pyrochemical compatibility between the simulated fuel and candidate material for cladding, and entrusted to Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).
Takaki, Seiya; Takano, Masahide
no journal, ,
Nitride fuel with ZrN or TiN matrix have been studied for transmutation of minor actinide (MA). These are supposed to be designed as solid solution or compounds with MA nitride from 20 mol% to 40 mol%. From the above, composition and temperature dependence of thermal conductivity for safety evaluation of the fuel have been studied with a little of MA. In the present study, we are aimed to clarify composition and temperature dependence of thermal conductivity and electric conductivity of DyZrN solid solution as MA surrogate nitride fuel in order to understand the thermal conduction mechanism of MA nitride fuel physically. In addition to, we introduce studies about pyrochemical compatibility between DyZrN (x=0, 0.3) and candidate material for cladding, and entrusted to Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).
Takaki, Seiya; Takano, Masahide
no journal, ,
Nitride fuel with ZrN matrix have been studied for transmutation of minor actinide (MA). These are supposed to be designed as ZrN solid solution or TiN compounds with MA nitride from 20 mol% to 40 mol%. From the above, composition and temperature dependence of thermal conductivity for safety evaluation of the fuel have been studied with a little of MA. In future, it is important to understand the heat conduction mechanism in detail when evaluating irradiation effect on thermal conductivity. In the present study, we are aimed to clarify composition and temperature dependence of thermal conductivity of DyZrN solid solution as surrogate nitride fuel with MA in order to understand the dependence of the MA nitride fuel physically.
, ThO, UO, NpO, PuO and AmOKato, Masato
no journal, ,
Morimoto, Kyoichi; Ogasawara, Masahiro*
no journal, ,
The heat capacity of MOX fuel is one of important thermophysical properties for the evaluation of its thermal conductivity and for the evaluations of transient event and severe accident of nuclear reactor. In this study, MOX sample with Pu-content of nearly 50% (50%Pu-MOX) was measured because it was predicted that the influence of Pu addition appeared to be significant. The raw material powder was cold-pressed and was sintered to make pellet. The oxygen to metal ratio of this pellet was adjusted to 2.00. The enthalpy of this sample was measured with drop calorimeter in in high temperature range. The rhenium container was used to prevent the reaction between the sample and the sample container. It was found that the enthalpy increased at a nearly constant rate up to about 1900 K with increasing temperature and that its rate rose at about 1900 K or more. It means that the heat capacity is approximately constant up to 1900K and starts to rise at about 1900K.
in high temperature regionMorimoto, Kyoichi; Ogasawara, Masahiro*
no journal, ,
The heat capacity of MOX fuel is one of important thermophysical properties for the evaluation of its thermal conductivity and for the evaluations of transient event and severe accident of nuclear reactor. In this study, MOX sample with Pu-content of nearly 50% (50%Pu-MOX) was measured because it was predicted that the influence of Pu addition appeared to be significant. The raw material powder was cold-pressed and was sintered to make pellet. The oxygen to metal ratio of this pellet was adjusted to 2.00. The enthalpy of this sample was measured with drop calorimeter in high temperature range. The rhenium container was used to prevent the reaction between the sample and the sample container. It was found that the enthalpy increased at a nearly constant rate up to about 1900K with increasing temperature and that its rate rose at about 1900K or more. It means that the heat capacity is approximately constant up to 1900K and starts to rise at about 1900K.
, 1; Experimental approachKato, Masato; Tsuchimochi, Ryota; Matsumoto, Taku; White, J.*; McClellan, K.*
no journal, ,
no abstracts in English
Morimoto, Kyoichi; Ogasawara, Masahiro*
no journal, ,
The heat capacity of MOX fuel is one of the important thermophysical properties. To evaluate the heat capacity of MOX fuel, the heat capacity of PuO is required because the heat capacity of MOX fuel is generally calculated from the compositional average of those of UO and PuO. The experimental results of the heat capacity of PuO are very scarce. In this study, the enthalpy of PuO pellet was measured in the temperature range from 980 to 2160 K with a drop calorimeter. In the measurement, the pellet was loaded in a tungsten container and a rhenium inner container was applied to prevent the reaction between the specimen and the tungsten container. It was found that the enthalpy increased at a constant rate with increasing temperature up to about 1900 K, and that above about 1900 K, its rate tended to increase with increasing temperature. It means that the heat capacity is raised when temperature exceeds about 1900 K.
Oishi, Yuji*; Takatani, Tomoya*; Fujieda, Shun*; Muta, Hiroaki*; Kondo, Toshiki; Kikuchi, Shin
no journal, ,
no abstracts in English
