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Journal Articles

Distinctive radiation durability of an ion exchange membrane in the SPE water electrolyzer for the ITER water detritiation system

Iwai, Yasunori; Yamanishi, Toshihiko; Isobe, Kanetsugu; Nishi, Masataka; Yagi, Toshiaki; Tamada, Masao

Fusion Engineering and Design, 81(1-7), p.815 - 820, 2006/02

 Times Cited Count:15 Percentile:70.41(Nuclear Science & Technology)

Solid-polymer-electrolyte (SPE) water electrolysis is attractive in electrolytic process of water detritiation system (WDS) in fusion reactors because it can electrolyze liquid waste directly, but radioactive durability of its ion exchange membrane is a key point. Radioactive durability of Nafion, a typical commercial ion exchange membrane, was experimentally investigated using Co-60 irradiation facility and electron beam irradiation facility at Takasaki Radiation Chemistry Research Establishment of JAERI. Nafion is composed of PTFE (Polytetrafluoroethylene) main chain. However the degradation of its mechanical strength by irradiation was significantly distinguished from that of PTFE and no serious damage was observed for its ion exchange capacity up to 530 kGy, the requirement of ITER. Atmospheric effects such as soaking and oxygen on degrading behaviors were discussed from the viewpoint of radical reaction mechanism. Dependencies of operating temperature and radioactive source are also demonstrated in detail.

JAEA Reports

Study on mutual permeation of hydrogen isotope through metal; Mutual permeation of hydrogen and deuterium through inconel 600

Takeda, Tetsuaki; Iwatsuki, Jin*

JAERI-Research 2000-057, 17 Pages, 2001/01

JAERI-Research-2000-057.pdf:1.58MB

no abstracts in English

Journal Articles

Permeation of hydrogen isotope in the HTTR hydrogen production system

Takeda, Tetsuaki; Iwatsuki, Jin*; Ogawa, Masuro

Nihon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, 4, p.405 - 406, 2000/00

no abstracts in English

Journal Articles

Study on tritium/hydrogen permeation in the HTTR hydrogen production system

Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

JAEA Reports

Study on tritium・hydrogen permeation in the HTTR hydrogen production system, 1; Hydrogen permeability of Hastelloy XR (Contract research)

Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro

JAERI-Tech 98-044, 34 Pages, 1998/11

JAERI-Tech-98-044.pdf:2.0MB

no abstracts in English

Journal Articles

Radiation effects and safety control of tritium

Yamaguchi, Takenori; Noguchi, Hiroshi

Nihon Genshiryoku Gakkai-Shi, 39(11), p.940 - 941, 1997/00

no abstracts in English

Journal Articles

Development of compact tritium confinement system using gas separation membrane

Hayashi, Takumi; Okuno, Kenji

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, p.205 - 207, 1994/06

no abstracts in English

JAEA Reports

Permeabilities of Hydrogen Isotopes Through Pd-25 wt% Ag Alloy Membrane at Comparatively High Pressure and Temperature

; Shimizu, Toku; ; Naruse, Yuji

JAERI-M 9677, 24 Pages, 1981/09

JAERI-M-9677.pdf:0.67MB

no abstracts in English

JAEA Reports

Sparation of Argon Isotopes by Porous Membrane Method(PartII); Separation Characteristics of Square Cascade at Total Reflux

; ; Saito, Keiichiro; ; Naruse, Yuji

JAERI-M 8374, 50 Pages, 1979/08

JAERI-M-8374.pdf:1.56MB

no abstracts in English

JAEA Reports

Separation of Gases by Porous Membrane Method

Naruse, Yuji;

JAERI-M 7858, 75 Pages, 1978/09

JAERI-M-7858.pdf:1.77MB

no abstracts in English

JAEA Reports

A Feasibility Study of Kr Removal Plant by Porous Membrane Method

Naruse, Yuji; ; ; ; Shimizu, Toku; Saito, Keiichiro

JAERI-M 7275, 40 Pages, 1977/09

JAERI-M-7275.pdf:1.07MB

no abstracts in English

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