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Journal Articles

A Quasi-classical trajectory calculation for the cesium exchange reaction of $$^{133}$$CsI (v = 0, j = 0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Cs

Kobayashi, Takanori*; Matsuoka, Leo*; Yokoyama, Keiichi

Nihon Enerugi Gakkai-Shi, 96(10), p.441 - 444, 2017/10

To investigate the reaction cross section of the cesium exchange reaction of $$^{133}$$CsI (v = 0, j = 0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Cs, we performed quasi-classical trajectory calculations on the potential energy surface calculated by the ab initio molecular orbital theory. The potential energy surface shows that intermediate Cs$$_{2}$$I is formed without entrance barrier and has two equivalent Cs-I bonds. The reaction cross sections decrease monotonically with increasing collision energy. The rate constant k (v = 0, j = 0) was estimated to be about 3$$times$$10$$^{-10}$$cm$$^{3}$$ molecule$$^{-1}$$s$$^{-1}$$ at temperatures ranging from 500 to 1200K and a slight negative temperature dependence was observed.

Journal Articles

Catalyst technology of Tanaka Kikinzoku Kogyo

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

JETI, 63(10), p.33 - 36, 2015/09

Tanaka Kikinzoku Kogyo provides a broad range of precious metals products and technologies. Tanaka Kikinzoku Kogyo and Japan Atomic Energy Agency have jointly 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 530 kGy, 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 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. It is also anticipated that the hydrophobic platinum catalyst manufacturing technology used for this catalyst could be applied to a wide range of fields other than nuclear fusion research. It was verified that if applied to a hydro oxidation catalyst, hydrogen could be efficiently oxidized, even at room temperature. This catalyst can also contribute to improving safety at non-nuclear plants that use hydrogen in general by solving the aforementioned vulnerability issue.

Journal Articles

Tritium release behavior from JT-60U vacuum vessel during air exposure phase and wall conditioning phase

Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Higashijima, Satoru; Nishi, Masataka; Konishi, Satoshi*; Nishikawa, Masabumi*; Tanabe, Tetsuo*

Fusion Science and Technology, 48(1), p.302 - 305, 2005/07

 Times Cited Count:5 Percentile:35.8(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Release behavior of hydrogen isotopes from JT-60U graphite tiles

Katayama, Kazunari*; Takeishi, Toshiharu*; Nagase, Hiroyasu*; Manabe, Yusuke*; Nishikawa, Masabumi*; Miya, Naoyuki; Masaki, Kei

Fusion Science and Technology, 48(1), p.561 - 564, 2005/07

 Times Cited Count:1 Percentile:10.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Isotope exchange reactions on ceramic breeder materials and their effect on tritium inventory

Nishikawa, Masabumi*; *; Kawamura, Yoshinori; Nishi, Masataka

JAERI-Conf 98-006, p.170 - 182, 1998/03

no abstracts in English

Journal Articles

Isotope exchange reaction in Li$$_{2}$$ZrO$$_{3}$$ packed bed

Kawamura, Yoshinori; Enoeda, Mikio; Okuno, Kenji

Fusion Engineering and Design, 39-40, p.713 - 721, 1998/00

 Times Cited Count:8 Percentile:57.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium inventory estimation in solid blanket system

Nishikawa, Masabumi*; Baba, Atsushi*; *; Kawamura, Yoshinori

Fusion Engineering and Design, 39-40, p.615 - 625, 1998/00

 Times Cited Count:14 Percentile:73.06(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Isotope exchange capacity of solid breeder materials

Baba, Atsushi*; Nishikawa, Masabumi*; Kawamura, Yoshinori; Okuno, Kenji

Journal of Nuclear Materials, 248, p.106 - 110, 1997/09

 Times Cited Count:4 Percentile:37.13(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Formation of water in lithium ceramics bed at hydrogen addition to purge gas

Kawamura, Yoshinori; Nishikawa, Masabumi*; *; Okuno, Kenji

Journal of Nuclear Materials, 230, p.287 - 294, 1996/00

 Times Cited Count:43 Percentile:94.61(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

None

Endo, Hideo; ; ; ; ; Nagai, Shuichiro

PNC TN8410 93-065, 192 Pages, 1993/04

PNC-TN8410-93-065.pdf:4.77MB

None

JAEA Reports

None

*; *; *; *; *

PNC TJ9124 93-010, 186 Pages, 1993/03

PNC-TJ9124-93-010.pdf:4.37MB

None

JAEA Reports

JAEA Reports

In-pile Test of Tritium Release from Lithium Oxide -Tritium Release Behavior-

Kurasawa, T.; ; ; ; ;

JAERI-M 84-087, 55 Pages, 1984/05

JAERI-M-84-087.pdf:2.12MB

no abstracts in English

Journal Articles

A New simulation procedure for multicomponent distillation column processing nonideal solutions or reactive solutions

*; *;

J.Chem.Eng.Jpn., 16(5), p.370 - 377, 1983/00

 Times Cited Count:24 Percentile:83.93(Engineering, Chemical)

no abstracts in English

Journal Articles

A Mathematical simulation procedure for multistage-type water/hydrogen exchange column in tritium system

; Naruse, Yuji

Nucl.Technol./Fusion, 3, p.112 - 120, 1982/00

no abstracts in English

Journal Articles

Removal mechanism of tritium by variously pretreated silica gel

Nakashima, Mikio; Tachikawa, Enzo; Saeki, Masakatsu;

Journal of Inorganic and Nuclear Chemistry, 43(2), p.369 - 373, 1981/00

 Times Cited Count:8 Percentile:37.91(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Determination of hydrogen in uranium metal by isotope exchange spectroscopic analysis method

Bunseki Kagaku, 14(2), P. 138, 1965/00

no abstracts in English

Oral presentation

Oxygen self-diffusion coefficients in mixed oxide fuel

Watanabe, Masashi; Kato, Masato; Sunaoshi, Takeo*

no journal, , 

The oxygen self-diffusion coefficients in mixed oxide (MOX) fuel are successfully measured using an isotope exchange method under H$$_{2}$$/H$$_{2}$$O atmosphere. These results are discussed with respect to the activation enthalpy of lattice defects.

Oral presentation

Oxygen self-diffusion coefficients in (U, Pu)O$$_{2pm}$$$$_{x}$$

Watanabe, Masashi; Sunaoshi, Takeo*; Kato, Masato

no journal, , 

no abstracts in English

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