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Journal Articles

Thermodynamic study of gaseous CsBO$$_{2}$$ by Knudsen effusion mass spectrometry

Nakajima, Kunihisa; Takai, Toshihide; Furukawa, Tomohiro; Osaka, Masahiko

Journal of Nuclear Materials, 491, p.183 - 189, 2017/08

 Times Cited Count:8 Percentile:61.27(Materials Science, Multidisciplinary)

One of the main chemical forms of cesium in the gas phase during severe accidents of light water reactor is expected to be cesium metaborate, CsBO$$_{2}$$, by thermodynamic equilibrium calculation considering reaction with boron. But accuracy of the thermodynamic data of gaseous metaborate, CsBO$$_{2}$$(g), has been judged as poor quality. Thus, Knudsen effusion mass spectrometric measurement of CsBO$$_{2}$$ was carried out to obtain reliable thermodynamic data. The evaluated values of standard enthalpy of formation of CsBO$$_{2}$$(g), $$Delta$$$$_{f}$$H$$^{circ}$$$$_{298}$$(CsBO$$_{2}$$,g), by the 2nd and 3rd law treatments are -700.7$$pm$$10.7 kJ/mol and -697.0$$pm$$10.6 kJ/mol, respectively, and agree with each other within the errors, which suggests our data are reliable. Further, it was found that the existing data of the Gibbs energy function and the standard enthalpy of formation agreed well with the values evaluated in this study, which indicates the existing thermodynamic data are also reliable.

Journal Articles

Oxide-metal ratio dependence of central void formation of mixed oxide fuel irradiated in fast reactors

Ikusawa, Yoshihisa; Maeda, Koji; Kato, Masato; Uno, Masayoshi*

Nuclear Technology, 199(1), p.83 - 95, 2017/07

 Times Cited Count:4 Percentile:37.06(Nuclear Science & Technology)

Based on thermal computation results obtained using an irradiation behavior analysis code, we have evaluated the effect of O/M ratio on fuel restructuring from the results of PIEs for the B14 irradiation test fuel, which was a mixed oxide fuel and was irradiated in the experimental reactor Joyo. The thermal computation results showed that fuel restructuring in the stoichiometric oxide fuel was accelerated, though the fuel temperature in the stoichiometric oxide fuel was evaluated as lower than that of the hypo-stoichiometric one. We explained this behavior as follows: first, the fuel temperature decreased due to the high thermal conductivity at stoichiometry; second, the pore migration velocity increased due to the increase in vapor pressure caused by the high vapor pressure of UO$$_{3}$$, which was derived from the high oxygen potential at stoichiometry. In addition, our results indicated that the central void diameter strongly depended on not only fuel temperature, but also vapor pressure.

Journal Articles

Vapor species evolved from Li$$_{2}$$TiO$$_{3}$$ heated at high temperature under various conditions

Hoshino, Tsuyoshi; Yasumoto, Masaru*; Tsuchiya, Kunihiko; Hayashi, Kimio; Nishimura, Hidetoshi*; Suzuki, Akihiro*; Terai, Takayuki*

Fusion Engineering and Design, 81(1-7), p.555 - 559, 2006/02

 Times Cited Count:18 Percentile:76.2(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Impact of interfaces on nuclear materials

Yamawaki, Michio*; Yamaguchi, Kenji; Suzuki, Atsushi*

Ionics, 7(4-6), p.339 - 345, 2001/07

 Times Cited Count:6 Percentile:37.52(Chemistry, Physical)

no abstracts in English

JAEA Reports

The development of mass balance estimation code; The development and the analyzed example with object type code(I)

;

JNC TN9400 2000-034, 48 Pages, 2000/03

JNC-TN9400-2000-034.pdf:1.56MB

The study and the development to put FBR (Fast Breeder Reactor) to practical use have been doing. So many kinds of technologies are investigated to construct nuclear fuel recycle received to the society. The most important aim of reprocessing has been to extract U and Pu from spent fuels effectively, but, now, the demands for reprocessing are many kinds on nuclear fuel recycle system's construction. These need to be accepted sufficiently. The system that consists of electrolysis, extraction, with molten salt and melting metal, volatilization and condensation using the difference of vapor pressure is suggested, because, differently from LWR (Light Water Reactor), FBR can use the low decontamination factor's fuel. When the engineering scale plant is designed, the dry reprocessing has unsolved problems(ex. process flow) because of less demonstrative scale plants of the dry reprocessing than ones of the wet reprocessing. So the analysis and the estimation of mass balance that is most fundamental in the dry reprocessing system's design need to keep up with the system's alteration (to add new processes etc.) flexibly. This study aim is to develop the mass balance estimation code of dry reprocessing that satisfies the demand mentioned above.

JAEA Reports

Study on fission product behaviors with strong radioactivity in severe accidents

Yamawaki, Michio*; Yamaguchi, Kenji*; Ono, Futaba*; Huang, J.*; Harada, Yuhei; Hidaka, Akihide; Sugimoto, Jun

JAERI-Tech 2000-015, p.38 - 0, 2000/03

JAERI-Tech-2000-015.pdf:1.31MB

no abstracts in English

Journal Articles

Vaporization properties of SrUO$$_{3}$$ and BaUO$$_{3}$$ in atmospheres simulating accident conditions

Huang, J.*; *; Yamaguchi, Kenji*; *; *;

Journal of Nuclear Materials, 248, p.257 - 261, 1997/00

 Times Cited Count:6 Percentile:47.96(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Properties of neptunium-plutonium mixed nitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa;

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.347 - 357, 1997/00

no abstracts in English

Journal Articles

Mass spectrometric investigation of the vapor over the LnCl$$_{3}$$-KCl equimolar melt (Ln=Nd,Er) at high temperatures

*; *; Hashimoto, Masashi; Kudo, Hiroshi

Bulletin of the Chemical Society of Japan, 69(2), p.353 - 357, 1996/00

 Times Cited Count:19 Percentile:68(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

Metallic ion generation from ceramic rods by ECR ion source and thermodynamic feature of vaporization

Yokota, Wataru; Nara, Takayuki; Arakawa, Kazuo; *; *

Nuclear Instruments and Methods in Physics Research B, 122(1), p.141 - 148, 1996/00

 Times Cited Count:2 Percentile:30.98(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Research on actinide mononitride fuel

Arai, Yasuo; ; Handa, Nuneo

Global 1995, Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems,Vol. 1, 0, p.538 - 545, 1995/00

no abstracts in English

Journal Articles

Structural stability and thermodynamic properties of Zr-N alloys

Ogawa, Toru

Journal of Alloys and Compounds, 203, p.221 - 227, 1994/00

 Times Cited Count:8 Percentile:57.78(Chemistry, Physical)

no abstracts in English

Journal Articles

Vaporization behavior of plutonium-zirconium binary alloy

Maeda, Atsushi; ; Okamoto, Yoshihiro; Omichi, Toshihiko

Journal of Alloys and Compounds, 205, p.35 - 38, 1994/00

 Times Cited Count:12 Percentile:66.82(Chemistry, Physical)

no abstracts in English

Journal Articles

Mass spectrometric study of ternary compounds PuMC$$_{2}$$(M=Fe.Co,Ni)

; ; ;

Journal of Nuclear Materials, 115, p.187 - 191, 1983/00

 Times Cited Count:0 Percentile:0.02(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Water Adsorption on Lithium Oxide Pellets in Helium Sweep Gas Stream

; Konishi, Satoshi; ; Kurasawa, T.; ; Katsuta, Hiroji; ; Naruse, Yuji

JAERI-M 82-194, 47 Pages, 1982/12

JAERI-M-82-194.pdf:1.44MB

no abstracts in English

Journal Articles

Behavior of ruthenium in fluoride-volatility processes, 3; Thermal decomposition of RuOF$$_{4}$$

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J.Phys.Chem., 82(7), p.780 - 784, 1978/07

no abstracts in English

JAEA Reports

Corrosion of AISI316 and AISI304 Stainless Steel with Iodine Vapour

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JAERI-M 5946, 24 Pages, 1975/01

JAERI-M-5946.pdf:1.07MB

no abstracts in English

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 3; Development of equilibrium vapor pressure measurement technique for FP compound

Takai, Toshihide; Nakajima, Kunihisa; Furukawa, Tomohiro; Osaka, Masahiko

no journal, , 

To develop reliable thermodynamic database of fission products is necessary for more accurate evaluation of fission product release and transport behavior using progression process analysis code under severe accident. This presentation introduces maintenance situation of high temperature mass spectrometer and reliability evaluation result.

Oral presentation

Development of measurement technique on the equilibrium vapor pressure of simulated fission products

Takai, Toshihide; Nakajima, Kunihisa; Furukawa, Tomohiro; Osaka, Masahiko

no journal, , 

Improvement of the serve accident analysis code is important to evaluate the distribution of the released fission products (FPs) in the reactor more precisely from the view point of both the removal preparation of the fuel debris in the Fukushima Daiichi Nuclear Power Station and improved source term evaluation. The development of the calculation model, which can evaluate the effect of atmosphere and the chemical reaction between the released FPs and control rod material (B$$_{4}$$C) at elevated temperature, is important for this purpose. The measurement technique of the equilibrium vapor pressure using a high temperature mass spectrometer was under development to expand the thermodynamic database of the simulated FPs, because the chemical equilibrium analysis plays an important role to clarify the effect of chemical reactions. In this study, the apparatus was developed for the equilibrium vapor pressure measurements, and then the reliability of measurement results was evaluated.

Oral presentation

24 (Records 1-20 displayed on this page)