JOPSS - Search Results

Hirohata, Yuko*; Shibahara, Takahiro*; Tanabe, Tetsuo*; Oya, Yasuhisa*; Arai, Takashi; Goto, Yoshitaka*; Masaki, Kei; Yagyu, Junichi; Oyaizu, Makoto*; Okuno, Kenji*; et al.

Fusion Science and Technology, 48(1), p.557 - 560, 2005/07

https://doi.org/10.13182/FST05-A986

Times Cited Count：3 Percentile：24.17(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Impurity release and deuterium retention properties of a ferritic steel wall in JFT-2M

Ogawa, Hiroaki; Yamauchi, Yuji*; Tsuzuki, Kazuhiro; Kawashima, Hisato; Sato, Masayasu; Shinohara, Koji; Kamiya, Kensaku; Kasai, Satoshi; Kusama, Yoshinori; Yamaguchi, Kaoru*; et al.

Journal of Nuclear Materials, 329-333(Part1), p.678 - 682, 2004/08

https://doi.org/10.1016/j.jnucmat.2004.04.192

Times Cited Count：4 Percentile：29.18(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal desorption of deuterium from ion irradiated Be $_{12}$ Ti

Iwakiri, Hirotomo*; Yasunaga, Kazufumi*; Yoshida, Naoaki*; Uchida, Munenori*; Kawamura, Hiroshi

Journal of Nuclear Materials, 329-333(Part A), p.880 - 884, 2004/00

https://doi.org/10.1016/j.jnucmat.2004.04.280

Times Cited Count：8 Percentile：48.76(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Characteristics of boundary plasmas after the removal of divertor baffle plates and boronization on JFT-2M

Kawashima, Hisato; Sengoku, Seio; Tsuzuki, Kazuhiro; Ogawa, Hiroaki; Kimura, Haruyuki

Journal of Nuclear Materials, 313-316, p.1338 - 1342, 2003/03

https://doi.org/10.1016/S0022-3115(02)01516-7

Times Cited Count：3 Percentile：25.75(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of a micro gas chromatograph for the analysis of hydrogen isotope gas mixtures in the fusion fuel cycle

Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka

Fusion Engineering and Design, 58-59, p.389 - 394, 2001/11

https://doi.org/10.1016/S0920-3796(01)00378-7

Times Cited Count：26 Percentile：85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of hydrogen isotopes with a micro gas chromatograph

Kawamura, Yoshinori; Iwai, Yasunori; Yamanishi, Toshihiko; Konishi, Satoshi; Nishi, Masataka

Fusion Engineering and Design, 49-50, p.855 - 861, 2000/11

https://doi.org/10.1016/S0920-3796(00)00302-1

Times Cited Count：28 Percentile：84.28(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Fujisaku, Kazuhiko*; Ishibashi, Yuzo; Takeda, Seiichiro; ; *

PNC TN8410 98-115, 50 Pages, 1998/09

PNC-TN8410-98-115.pdf:1.48MB

None

Journal Articles

Tritium retention in CX-2002U and methods to reduce tritium inventory

Tadokoro, Takahiro*; Ohira, Shigeru; Nishi, Masataka; Isobe, Kanetsugu*

Journal of Nuclear Materials, 258-263, p.1092 - 1096, 1998/00

https://doi.org/10.1016/S0022-3115(98)00280-3

Times Cited Count：3 Percentile：31.81(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

ATR Demonstration reactor integrity verification test for the pressur tube rolled joint portion (Fiscal 1988)

; ; ; ;

PNC TN9410 94-052, 251 Pages, 1994/01

PNC-TN9410-94-052.pdf:9.33MB

The structure of the pressure tube rolled joint portion for the ATR Demonstration Reactor is somewhat changed from that for Fugen, in order reduce the residual stress around the portion. Therefore, Constant Temperature Endurance Test and Thermal Cycle Endurance Test have been conducted under the reactor operating conditions except irradiation to examine the rolled joint integrity. (1)Constant Temperature Endurance Test. In fiscal 1988, Constant Temperature Endurance Test have been performed in the Component Test Loop for 2,033 hours under the reactor operating conditions (pressure 75kg/cm $^{2}$ , temperature 280 $^{circ}$ C) for the JP-3 specimen (total testing period 4,033 hours) and the JP-4, JP-5 specimens (total testing period 9,533 hours). After the endurance test it was found by the helium leak test that the rolled joint tightness was maintained enough. Therefore, it was confirmed that the reduction of the residual atress at the rolled joint portion which occurred at the initial stage of the operation did not affect the rolled joint tightness. (2)Thermal Cycle Endurance Test. The helium leak test and the ultrasonic flaw detection test were performed before and after Thermal Cycle Endurance Test (the unmber of thermal cycle increaced from 60 times to 140 times in fisical 1988), of which results showed the integrity of the rolled joint tightness and no crack propagation near the rolled joint portion. Therefore, it was confirmed that 140 times thermal cycle which was the design value for the reactor life of 30 years did not affect the rolled joint tightness and the initiation and propagation of a crack even for the specimen with 200 ppm hydrogen.