Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 25

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of hydrophobic platinum catalyst for the effective collection of tritium in fusion plants

Iwai, Yasunori; Kubo, Hitoshi*; Oshima, Yusuke*

Isotope News, (736), p.12 - 17, 2015/08

We have successfully developed a new hydrophobic platinum catalyst for collecting tritium at nuclear fusion reactors. Catalysts used to collect tritium are called hydrophobic precious metal catalysts. In Japan, hydrophobic precious metal catalysts manufactured from polymers have been used for heavy water refinement.However, this catalyst has issues related to embrittlement to radiation and thermal stability. These technological issues needed to be solved to allow for its application to nuclear fusion reactors requiring further enrichment from highly-concentrated tritiated water. We developed a new method of manufacturing catalysts involving hydrophobic processing with an inorganic substance base. As a result, previous technological issues were able to be solved with the development of a catalyst that exhibited no performance degradation in response to radiation application of 530kGy, a standard for radiation resistance, and maintenance of thermal stability at over 600$$^{circ}$$C, which is much higher than the 70$$^{circ}$$C temperature that is normally used. The catalyst created with this method was also confirmed to have achieved the world's highest exchange efficiency, equivalent to 1.3 times the previously most powerful efficiency. The application of this catalyst to the liquid phase catalytic exchange process is expected to overcome significant technological hurdles with regards to improving the reliability and efficiency of systems for collecting tritium from tritiated water.

Journal Articles

Characterization of JT-60U exhaust gas during experimental operation

Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Tsuzuki, Kazuhiro; Higashijima, Satoru; Nishi, Masataka; Kobayashi, Yasunori*; Konishi, Satoshi*

Fusion Engineering and Design, 81(1-7), p.827 - 832, 2006/02

 Times Cited Count:11 Percentile:60.11(Nuclear Science & Technology)

Exhaust gas from JT-60U during experimental operation has been measured with Gas Chromatography (GC), and the gas exhaust characteristic from JT-60U on plasma discharge conditions has been investigated during the JT-60U experimental campaign in 2003-2004. During experimental operation of JT-60U, hydrogen isotope concentration strongly depended on the type of discharges such as high performance, long pulse and so on. On the other hand, impurity species, such as helium, hydrocarbon and carbon oxide, were detected during plasma discharges occasionally. During the experimental operation, plasma disruption remarkably tended to produce high concentration impurities. Glow discharge and Taylor discharge for wall conditioning also produced impurities. In the case of normal plasma, impurity was detected and high performance plasma, such as high $$beta$$ plasma, tended to produce high concentration impurities. This result indicated that impurities concentration might be higher in the case of normal plasma in ITER, because of its high performance.

Journal Articles

Interlinked test results for fusion fuel processing and blanket tritium recovery systems using cryogenic molecular sieve bed

Yamanishi, Toshihiko; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Isobe, Kanetsugu; Uzawa, Masayuki*; Nishi, Masataka

Fusion Science and Technology, 48(1), p.63 - 66, 2005/07

 Times Cited Count:6 Percentile:40.41(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experiments of continuous gas separation for D$$_{2}$$/He mixed gas under room temperature

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya

Shinku, 46(3), p.154 - 157, 2003/03

no abstracts in English

Journal Articles

H-D-T cryogenic distillation experiments at TPL/JAERI in support of ITER

Iwai, Yasunori; Yamanishi, Toshihiko; Ohira, Shigeru; Suzuki, Takumi; Shu, Wataru; Nishi, Masataka

Fusion Engineering and Design, 61-62, p.553 - 560, 2002/11

 Times Cited Count:15 Percentile:65.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study on sudden loss of cryogenic coolant accident happened in the hydrogen isotope separation system for fusion reactor

Iwai, Yasunori; Nakamura, Hirofumi; Konishi, Satoshi; Nishi, Masataka; Willms, R. S.*

Fusion Science and Technology, 41(3), p.668 - 672, 2002/05

no abstracts in English

Journal Articles

A Design study of advanced hydrogen isotope separation system for ITER

Iwai, Yasunori; Yamanishi, Toshihiko; Nishi, Masataka

Fusion Technology, 39(2-Part2), p.1078 - 1082, 2001/03

no abstracts in English

Journal Articles

Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute

Nishi, Masataka; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Isobe, Kanetsugu; Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Suzuki, Takumi; et al.

Fusion Engineering and Design, 49-50, p.879 - 883, 2000/11

 Times Cited Count:4 Percentile:32.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of a tritium fuel processing systems using an electrolytic reactor for ITER

Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Arita, Tadaaki*; Maruyama, T.*; Kakuta, Toshiya*; Konishi, Satoshi; Enoeda, Mikio; Ohira, Shigeru; Hayashi, Takumi; et al.

Nuclear Fusion, 40(3Y), p.515 - 518, 2000/03

 Times Cited Count:6 Percentile:20.97(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Development of dynamic simulation code for fuel cycle of fusion reactor

Aoki, Isao; Seki, Yasushi; *; *; Kim, Y.*

JAERI-Data/Code 99-004, 136 Pages, 1999/02

JAERI-Data-Code-99-004.pdf:5.82MB

no abstracts in English

Journal Articles

Demonstration of the integrated fusion fuel loop at the tritium process laboratory of the Japan Atomic Energy Research Institute

Yamanishi, Toshihiko; Konishi, Satoshi; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Maruyama, T.*; Kakuta, Toshiya*; Ohira, Shigeru; Nakamura, Hirofumi; Kobayashi, Kazuhiro; et al.

Fusion Technology, 34(3), p.536 - 540, 1998/11

no abstracts in English

Journal Articles

Status of the ITER tritium plant design

Yoshida, Hiroshi; O.Kveton*; J.Koonce*; D.Holland*; Haange, R.*

Fusion Engineering and Design, 39-40, p.875 - 882, 1998/00

 Times Cited Count:25 Percentile:85.88(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of dynamic simulation code for fuel cycle of fusion reactor; Single pulse operation simulation

Aoki, Isao; Seki, Yasushi; *; *; C.Kim*

JAERI-Data/Code 97-042, 113 Pages, 1997/11

JAERI-Data-Code-97-042.pdf:3.59MB

no abstracts in English

Journal Articles

Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly

Konishi, Satoshi; Yamanishi, Toshihiko; Enoeda, Mikio; Hayashi, Takumi; Ohira, Shigeru; Yamada, Masayuki; Suzuki, Takumi; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; et al.

Fusion Engineering and Design, 28, p.258 - 264, 1995/00

 Times Cited Count:4 Percentile:43.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Tritium test of the tritium processing components under the Annex III US-Japan collaboration; Annex III final report

Konishi, Satoshi; Yoshida, Hiroshi; Naruse, Yuji; K.E.Binning*; R.V.Carlson*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-M 93-090, 21 Pages, 1993/03

JAERI-M-93-090.pdf:0.6MB

no abstracts in English

JAEA Reports

Tests of the JAERI fuel cleanup system with deuterium at the Tritium Systems Test Assembly; JFCU stand alone deuterium test, JFCU stand alone deuterium test 2

Konishi, Satoshi; Ohira, Shigeru; Hayashi, Takumi; Inoue, Masahiko*; Watanabe, Tetsuo*; Naruse, Yuji; Okuno, Kenji; Barnes, J. W.*; W.Harbin*; Bartlit, J. R.*; et al.

JAERI-M 93-089, 46 Pages, 1993/03

JAERI-M-93-089.pdf:1.26MB

no abstracts in English

JAEA Reports

Test of the palladium diffuser in the JAERI fuel cleanup system in the Tritium Systems Test Assembly

Konishi, Satoshi; Ohira, Shigeru; Hayashi, Takumi; Watanabe, Tetsuo*; Inoue, Masahiko*; Naruse, Yuji; Okuno, Kenji; Barnes, J. W.*; W.Harbin*; Bartlit, J. R.*; et al.

JAERI-M 93-088, 18 Pages, 1993/03

JAERI-M-93-088.pdf:0.47MB

no abstracts in English

JAEA Reports

Test of the cold traps in the JAERI fuel cleanup system in the Tritium Systems Test Assembly

Ohira, Shigeru; Konishi, Satoshi; Naruse, Yuji; Okuno, Kenji; Barnes, J. W.*; W.Harbin*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-M 93-087, 29 Pages, 1993/03

JAERI-M-93-087.pdf:0.62MB

no abstracts in English

JAEA Reports

Design of the JAERI fuel cleanup system for the tritium systems test assembly; System design description of the JAERI fuel cleanup system

Konishi, Satoshi; Hayashi, Takumi; Naruse, Yuji; Okuno, Kenji; R.V.Carlson*; Anderson, J. L.*

JAERI-M 93-086, 40 Pages, 1993/03

JAERI-M-93-086.pdf:1.35MB

no abstracts in English

JAEA Reports

Joint operation of TSTA under the collaboration between JAERI and DOE; TSTA loop run October 1990, from October 1990 tritium run test plan and result, TTA-TP-100-19

Konishi, Satoshi; Ohira, Shigeru; Inoue, Masahiko*; Watanabe, Tetsuo*; Naruse, Yuji; Okuno, Kenji; Barnes, J. W.*; Sherman, R. H.*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-M 93-085, 40 Pages, 1993/03

JAERI-M-93-085.pdf:0.8MB

no abstracts in English

25 (Records 1-20 displayed on this page)