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Journal Articles

Preliminary characterization of plasma-sintered beryllides as advanced neutron multipliers

Nakamichi, Masaru; Kim, Jae-Hwan; Munakata, Kenzo*; Shibayama, Tamaki*; Miyamoto, Mitsutaka*

Journal of Nuclear Materials, 442(1-3), p.S465 - S471, 2013/11

 Times Cited Count:10 Percentile:65.2(Materials Science, Multidisciplinary)

Journal Articles

Effect of cation exchange on hydrogen adsorption property of mordenite for isotope separation

Kawamura, Yoshinori; Iwai, Yasunori; Munakata, Kenzo*; Yamanishi, Toshihiko

Journal of Nuclear Materials, 442(1-3), p.S455 - S460, 2013/11

 Times Cited Count:10 Percentile:65.2(Materials Science, Multidisciplinary)

Zeolite easily exchanges its cation to another. In this work, synthetic mordenite type zeolite (Na-MOR) was used as start material. And, its cation (Na$$^{+}$$) has been exchanged by Li$$^{+}$$, K$$^{+}$$, Mg$$^{2+}$$ and Ca$$^{2+}$$. Then, adsorption capacities of H$$_{2}$$ and D$$_{2}$$ on them were investigated at 77 K, 159 K, 175 K and 195 K. Adsorption capacities on Li-MOR and Ca-MOR became larger than that on Na-MOR at low pressure range. Oppositely, that on K-MOR became smaller. In case of alkaline metal, cation with small atomic number may lead to large adsorption capacity.

Journal Articles

Adsorption behavior of hydrogen and deuterium on natural mordenite adsorbents at 77 K

Munakata, Kenzo*; Kawamura, Yoshinori

Fusion Science and Technology, 62(1), p.71 - 76, 2012/07

 Times Cited Count:4 Percentile:27.39(Nuclear Science & Technology)

Cryogenic adsorption is effective for the recovery of low-concentration hydrogen isotopes from bulk helium gases. As the result of screening test, it has been found out that a natural mordenite has a quite high adsorption capacity for H$$_{2}$$ and D$$_{2}$$ under the helium atmosphere at 77 K. In this work, the adsorption rates of hydrogen isotopes for the mordenite were quantified by analyzing breakthrough curves obtained in experiments. Evaluated effective pore diffusivities suggest that the mordenite is promising for the recovery of low concentration hydrogen isotopes from the helium bulk gas.

Journal Articles

Adsorption behavior of hydrogen isotopes on mordenite adsorbents at 77K

Munakata, Kenzo*; Kawamura, Yoshinori

Fusion Science and Technology, 60(1), p.426 - 430, 2011/07

 Times Cited Count:3 Percentile:27.67(Nuclear Science & Technology)

Cryogenic adsorption is effective for the recovery of hydrogen isotopes of small concentrations from the bulk helium gas. Thus, the cryogenic adsorption method is considered to be applied to the recovery of tritium from the blanket sweep gas which recovers tritium from ceramic breeder materials. The authors performed a screening test to find more suitable adsorbents for the recovery of hydrogen isotopes from the bulk helium gas at 77K. The screening test indicates that a natural mordenite adsorbent has a quite high adsorption capacity for hydrogen under the helium atmosphere. The adsorption rate of hydrogen isotopes was quantified by analyzing breakthrough curves obtained in the experiments. Evaluated effective pore diffusivities of hydrogen isotopes in the mordenite adsorbents are comparable to that in MS5A adsorbents. Thus, it can be said that mordenite adsorbents are also suitable for adsorption of hydrogen isotopes from the viewpoint of adsorption rates.

Journal Articles

Adsorption capacity of tritium on mordenite at low temperature

Kawamura, Yoshinori; Iwai, Yasunori; Hayashi, Takumi; Yamanishi, Toshihiko; Munakata, Kenzo*

Fusion Science and Technology, 56(1), p.168 - 172, 2009/07

 Times Cited Count:4 Percentile:32.2(Nuclear Science & Technology)

Synthesis zeolite is the candidate material of the separation column of the gas chromatograph for the hydrogen isotope analysis. Mordenite (MOR) is one of the zeolite, and has been reported that the MOR column can separate hydrogen isotope at about 200 K. So, the present authors have investigated the adsorption capacities of H$$_{2}$$ and D$$_{2}$$ on MOR at various temperatures, and have predicted the adsorption isotherms of HD, HT, DT and T$$_{2}$$. In this work, the adsorption capacities of tritium on MOR at 77 K and 87 K were investigated, and they were compared with the predicted isotherms. The observed isotherm at 87 K agreed with the predicted isotherm fairly well. However, at 77 K, the adsorption capacity at low presser region was smaller than the isotherm of D$$_{2}$$.

Journal Articles

Development of advanced tritium breeders and neutron multipliers for DEMO solid breeder blankets

Tsuchiya, Kunihiko; Hoshino, Tsuyoshi; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Terai, Takayuki*; Tanaka, Satoru*; Munakata, Kenzo*; Kato, Shigeru*; Uchida, Munenori*; et al.

Nuclear Fusion, 47(9), p.1300 - 1306, 2007/09

 Times Cited Count:20 Percentile:59.77(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Recent results on beryllium and beryllides in Japan

Mishima, Yoshinao*; Yoshida, Naoaki*; Kawamura, Hiroshi; Ishida, Kiyohito*; Hatano, Yuji*; Shibayama, Tamaki*; Munakata, Kenzo*; Sato, Yoshiyuki*; Uchida, Munenori*; Tsuchiya, Kunihiko; et al.

Journal of Nuclear Materials, 367-370(2), p.1382 - 1386, 2007/08

 Times Cited Count:25 Percentile:84.85(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of advanced tritium breeders and neutron multipliers for DEMO solid breeder blankets

Tsuchiya, Kunihiko; Hoshino, Tsuyoshi; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Terai, Takayuki*; Tanaka, Satoru*; Munakata, Kenzo*; Kato, Shigeru*; Uchida, Munenori*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

no abstracts in English

Journal Articles

Development of beryllides as advanced neutron multipliers for fusion blankets

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Tanaka, Satoru*; Uchida, Munenori*; Ishida, Kiyohito*; Shibayama, Tamaki*; Munakata, Kenzo*; Sato, Yoshiyuki*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 83(3), p.207 - 214, 2007/03

no abstracts in English

Journal Articles

Status of beryllium R&D in Japan

Kawamura, Hiroshi; Tsuchiya, Kunihiko; Mishima, Yoshinao*; Yoshida, Naoaki*; Munakata, Kenzo*; Ishida, Kiyohito*; Hatano, Yuji*; Shibayama, Tamaki*; Sato, Yoshiyuki*; Uchida, Munenori*; et al.

INL/EXT-06-01222, p.1 - 7, 2006/02

no abstracts in English

Journal Articles

Present status of beryllide R&D as neutron multiplier

Kawamura, Hiroshi; Takahashi, Heishichiro*; Yoshida, Naoaki*; Mishima, Yoshinao*; Ishida, Kiyohito*; Iwadachi, Takaharu*; Cardella, A.*; Van der Laan, J. G.*; Uchida, Munenori*; Munakata, Kenzo*; et al.

Journal of Nuclear Materials, 329-333(1), p.112 - 118, 2004/08

 Times Cited Count:31 Percentile:87.63(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Stability of titanium beryllide under water vapor

Munakata, Kenzo*; Kawamura, Hiroshi; Uchida, Munenori*

Journal of Nuclear Materials, 329-333(Part2), p.1357 - 1360, 2004/08

 Times Cited Count:10 Percentile:57.33(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Study on reactivity of titanium beryllide with water vapor

Munakata, Kenzo*; Kawamura, Hiroshi; Uchida, Munenori*

JAERI-Conf 2004-006, p.210 - 215, 2004/03

no abstracts in English

Oral presentation

The Annihilation behavior of irradiation defects induced by 14 MeV and thermal neutron irradiation in Li$$_{4}$$SiO$$_{4}$$

Nishikawa, Yusuke*; Oyaizu, Makoto*; Suda, Taichi*; Yoshikawa, Akira*; Shinozaki, Takashi*; Munakata, Kenzo*; Fujii, Toshiyuki*; Yamana, Hajimu*; Takakura, Kosuke; Ochiai, Kentaro; et al.

no journal, , 

no abstracts in English

Oral presentation

Design of LPCE column for performance tests on tritium separation with TLK facility

Sugiyama, Takahiko*; Yamanishi, Toshihiko; Munakata, Kenzo*; Asakura, Yamato*; Yamamoto, Ichiro*; Glugla, M.*

no journal, , 

We report a design of the column interior which was designed to fit into the existing facility dedicated for LPCE process characterization (under the limitation of the TLK facility). The experimental conditions such as liquid and gas flow-rates, temperature have been established during preliminary investigations carried out at Nagoya University. The column to be used in the TLK facility is stainless steel tube with 55 mm internal diameter and 2 m length. The tritium separation experiments are performed at 120 kPa, 343 K. A stage-wise model was also developed to predict separative performance of the column. This model requires the channeling coefficients. The channeling coefficient which represents axial dispersion of the packed bed is evaluated against flow rates of water by impulse response. Analytical results with the present model present effects of the catalysis quantity and the gas-liquid ratio on separative performances of the column.

Oral presentation

Reactivity of intermetallic compound of Ti and Be with water vapor - Be$$_{12}$$Ti prepared by plasma sintering method as a neutron multiplier candidate material

Wada, Kohei; Munakata, Kenzo*; Kim, Jae-Hwan; Nakamura, Ayano*; Nakamichi, Masaru

no journal, , 

The neutron multiplier is indispensable for generation of tritium that is a fuel of fusion reactors. Metallic beryllium is considered as a candidate for the neutron multiplier. However, metallic beryllium has high reactivity with oxygen and water vapor at high temperatures, and produces H$$_{2}$$ and BeO. This time, we performed hydrogen generation experiment, using Be$$_{12}$$Ti sample fabricated by a plasma-sintering method. After the experiment, the surface analysis of Be$$_{12}$$Ti was conducted.

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