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Journal Articles

The Effect of final heat treatment at fabrication on the terminal solid solubility of hydrogen in Zry-4

Yamauchi, Akihiro*; Amaya, Masaki

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 7 Pages, 2018/10

Differential scanning calorimetry (DSC) measurements on pre-hydrided cold worked, stress relieved and recrystallized Zry-4 cladding were performed in a temperature range between 50 and 600$$^{circ}$$C in order to elucidate the effect of final heat treatment at fabrication of Zircaloy-4 (Zry-4) cladding on the terminal solid solubility during the dissolution of zirconium hydrides at heating up (TSSD). Obtained DSC curves and Metallography indicate that the initial state of hydrides affects the dissolution behavior of hydride. The Arrhenius plots of the TSSD temperatures and hydrogen contents obtained from this study revealed that cold worked samples exhibited the largest TSSD and followed by stress relieved and recrystallized samples. The results of this study indicated that the difference in microstructure due to final heat treatment at fabrication of Zry-4 cladding affects the dissolution behavior of hydrides.

JAEA Reports

Investigation and basic evaluation for ultra-high burnup fuel cladding material

Ioka, Ikuo; Suga, Masataka*; Nagase, Fumihisa; Futakawa, Masatoshi; Kiuchi, Kiyoshi

JAERI-Tech 2001-013, 111 Pages, 2001/03

JAERI-Tech-2001-013.pdf:7.47MB

no abstracts in English

Journal Articles

Nuclear fuels and materials

Watanabe, Kazuo

Hyojun Busshitsu; Bunseki, Keisoku No Shinraisei Kakuho No Tameni, p.175 - 178, 1998/00

no abstracts in English

Journal Articles

Certified reference materials; Nulcear fuel and reactor materials

Watanabe, Kazuo

Bunseki, 0(3), p.196 - 197, 1996/00

no abstracts in English

Journal Articles

JAEA Reports

Integrity evaluations for the 2nd Fugen pressure tube surveillance test

; ; ; ; ; Shibahara, Itaru

PNC TN9410 92-321, 30 Pages, 1992/10

PNC-TN9410-92-321.pdf:0.67MB

Integrity evaluations have been performed for the 2nd Fugen pressure tube test (8 years irradiation, 5.6 $$times$$ 10$$^{21}$$n/cm$$^{2}$$ (E$$>$$1Mev)). Test items mainly consist of tensile test, bending test, corrosion test and hydrogen analysis. It has become clear using these data that the pressure tube material has maintained its integrity during the irradiation by the integrity assessment on both tensile and fracture toughness properties. Besides, both thickness loss by corrosion and absorbed hydrogen content were lower than those of design values.

Journal Articles

Simultaneous multielement analysis of zirconium alloys by chlorination separation/ICP-AES

Kato, Kaneharu

Bunseki Kagaku, 39(8), p.439 - 444, 1990/08

no abstracts in English

Journal Articles

Mechanical properties of chromic oxide coating film on zirconium alloy formed by chemical densified coating method

*; Kawamura, Hiroshi; *;

Nihon Seramikkusu Kyokai Gakujutsu Rombunshi, 98(1139), p.721 - 725, 1990/07

no abstracts in English

JAEA Reports

Determination of Carbon in Zircaloys

JAERI-M 83-035, 43 Pages, 1983/03

JAERI-M-83-035.pdf:1.4MB

no abstracts in English

JAEA Reports

None

Miura, Makoto; ; ; Omori, Takuro; ; Tanaka, Yasumasa; Shiina, Sadamu; Ogasawara, Koji

PNC TN841 79-12, 103 Pages, 1979/03

PNC-TN841-79-12.pdf:4.84MB

no abstracts in English

Journal Articles

Oral presentation

High temperature oxidation of Zr-35Cu alloy at 873 K

Nakahara, Kaito*; Kawada, Rio*; Irisawa, Eriko; Ueda, Mitsutoshi*; Kawamura, Kenichi*

no journal, , 

In order to develop oxygen sensor using oxide scales formed on the surface of zirconium alloy, we focused on zirconium and copper alloy system. It was expected that the oxide scale of Zr oxide on the alloy is thin and elaborate compared with that on the pure Zr because the activity of Zr in the alloy is reduced and the oxidation rate of alloy become slow. Therefore the oxidation behavior and mechanism of two phase alloy, Zr-35Cu which is composed of Zr$$_{2}$$Cu and Zr$$_{7}$$Cu$$_{10}$$, was studied. The results showed the oxidation rate of the alloy was same with that of the pure Zr.

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