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Journal Articles

Thermodynamic and thermophysical properties of the actinide nitrides

Uno, Masayoshi*; Nishi, Tsuyoshi*; Takano, Masahide

Comprehensive Nuclear Materials, 2nd Edition, Vol.7, p.202 - 231, 2020/08

On the thermodynamic and thermophysical properties of the actinide nitrides in Comprehensive Nuclear Materials published by Elsevier as the first edition in 2012, we have revised them by adding some brand-new data. The main topics added are the solid solubility of the actinide nitrides into the zirconium nitride matrix for transmutation fuel, the lattice expansion of actinide nitrides induced by self-irradiation damage, the influence of defects accumulation on thermal conductivity, and the thermal expansion in curium nitride lattice.

Journal Articles

Effect of absorbed hydrogen on the stress corrosion cracking (SCC) susceptibility of unirradiated Zircaloy cladding

Amaya, Masaki; Fuketa, Toyoshi

Journal of Nuclear Science and Technology, 41(11), p.1091 - 1099, 2004/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Effect of absorbed hydrogen on the stress corrosion cracking (SCC) susceptibility of unirradiated Zircaloy cladding was examined. The data obtained from literatures show that the ratios of SCC threshold stress ($$sigma$$$$_{th}$$) to 0.2% yield stress ($$sigma$$$$_{0.2}$$) in unirradiated Zircaloy claddings increase with increasing hydrogen contents below 60 ppm, irrespective of the kind of Zircaloy-2 and -4. Thermodynamic calculations were carried out for the reaction between iodine gas and zirconium containing hydrogen. The results suggested that the reactions hardly occurred at increased hydrogen content and zirconium reacted with iodine gas only below 90 ppm of hydrogen. Since these tendencies correspond to those of the ratios of $$sigma$$$$_{th}$$ to $$sigma$$$$_{0.2}$$ on the hydrogen content, it is considered that hydrogen affects the reactions between iodine gas and zirconium and reduces the SCC susceptibility of Zircaloy claddings.

Journal Articles

Thermochemical modeling of actinide alloys related to advanced fuel cycles

Ogawa, Toru; Akabori, Mitsuo; R.G.Haire*; Kobayashi, Fumiaki

Journal of Nuclear Materials, 247, p.215 - 221, 1997/00

 Times Cited Count:11 Percentile:66.72(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Estimation of thermodynamic properties of alloys from phase diagram and other weak boundary conditions

Ogawa, Toru; Iwai, Takashi

JAERI-M 89-063, 46 Pages, 1989/05

JAERI-M-89-063.pdf:1.1MB

no abstracts in English

Journal Articles

Theoretical estimatuion of thermodynamic properties of metallic fuel

Ogawa, Toru; Iwai, Takashi

FBR Kinzoku Nenryo Saikuru No Seiritsusei Hyoka, Kinzoku Nenryo Kyodo Kaiseki Kodo No Kaihatsu, Sono 2; Kani Kaiseki Kodo No Kairyo, Kensho To Shosai Kaiseki Kodo No Kihon Sekkei, Denryoku Chuo Kenkyusho Hokoku, p.232 - 244, 1989/00

no abstracts in English

Journal Articles

Measurements of O/U ratio and oxygen potential for UO$$_{2}$$$$_{+}$$$$_{chi}$$(0≦x≦0.1)

Ugajin, Mitsuhiro

Journal of Nuclear Science and Technology, 20(3), p.228 - 236, 1983/00

 Times Cited Count:17 Percentile:84.59(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Data and Phase Diagram of Liquid Metals and Inorganic Molten Salts: Li$$_{2}$$BeF$$_{4}$$

; ; Furukawa, Kazuo

JAERI-M 4750, 49 Pages, 1972/03

JAERI-M-4750.pdf:0.86MB

no abstracts in English

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