Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 31

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

Trial synthesis of Li$$_{2}$$Be$$_{2}$$O$$_{3}$$ for high-functional tritium breeders

Hoshino, Tsuyoshi; Oikawa, Fumiaki; Natori, Yuri*; Kato, Kenichi*; Sakka, Tomoko*; Nakamura, Mutsumi*; Tatenuma, Katsuyoshi*

Fusion Engineering and Design, 88(9-10), p.2268 - 2271, 2013/10

 Times Cited Count:1 Percentile:12.53(Nuclear Science & Technology)

Lithium titanate with additional Li (Li$$_{2+x}$$TiO$$_{3+y}$$) and lithium orthosilicate (Li$$_{4}$$SiO$$_{4}$$) is one of the most promising candidates for use in a tritium breeder because of its good chemical and mechanical stabilities. Currently, mixtures of tritium breeder pebble and neutron multiplier (Be or Be$$_{12}$$Ti) pebble are being considered for use in increasing the tritium breeding ratio in a breeding blanket. However, lithium and beryllium are gradually reacted under practical operating conditions, and therefore a high-functional tritium breeder such as lithium beryllium oxide (Li$$_{2}$$Be$$_{2}$$O$$_{3}$$) needs to be developed to compensate for this reactive characteristic under high temperature use. In this study, methods of synthesizing Li$$_{2}$$Be$$_{2}$$O$$_{3}$$ have been extensively investigated by means of solid-phase reaction. The solid-phase reaction of LiOH(H$$_{2}$$O) and BeO is a suitable synthesis method for lithium beryllium oxide (Li$$_{2}$$Be$$_{2}$$O$$_{3}$$). It is expected that single-phase Li$$_{2}$$Be$$_{2}$$O$$_{3}$$ will be stable under the mixture conditions of a tritium breeder and neutron multiplier in the blanket region at high temperatures.

Journal Articles

Advanced-ORIENT cycle, its scientific progress and prospect for engineering feasibility

Koyama, Shinichi; Yamagishi, Isao; Suzuki, Tatsuya*; Ozawa, Masaki*; Fujita, Reiko*; Okada, Ken*; Tatenuma, Katsuyoshi*; Mimura, Hitoshi*; Fujii, Yasuhiko

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12

Effective separation of MA and LLFP, transmutation and utilization were the main directions of Advanced OREINT Cycle project. Study for each integrant technology was concluded as first trial of the project. TPR enabled to separate MA/Ln and then Am/Cm precisely from spent fuel in HCl and HNO$$_{3}$$ media. CEE method could separate the light PGM and Tc by HCl media. Recovery of Cs from simulated HLLW coul be achieved more than 90 %. In addition, the perspective for next phase was proposed.

Journal Articles

Development of advanced tritium breeding material with added lithium for ITER-TBM

Hoshino, Tsuyoshi; Kato, Kenichi*; Natori, Yuri*; Oikawa, Fumiaki; Nakano, Natsuko*; Nakamura, Mutsumi*; Sasaki, Kazuya*; Suzuki, Akihiro*; Terai, Takayuki*; Tatenuma, Katsuyoshi*

Journal of Nuclear Materials, 417(1-3), p.684 - 687, 2011/10

 Times Cited Count:39 Percentile:95.49(Materials Science, Multidisciplinary)

Lithium titanate (Li$$_{2}$$TiO$$_{3}$$) is one of the most promising candidates among tritium breeding materials because of its good tritium release. Addition of H$$_{2}$$ to inert sweep gas has been proposed for enhancing the tritium release from tritium breeding materials. However, the mass of Li$$_{2}$$TiO$$_{3}$$ was decreased with time in the hydrogen atmosphere. It is assumed that the mass decrease indicates the loss of the oxygen contained in the sample caused by the change from Ti $$^{4+}$$ to Ti $$^{3+}$$, and that the partial pressures of Li-containing species were increased in the hydrogen atmosphere. In order to decrease the mass-change at high temperature, advanced tritium breeding material with added Li should be developed to improve the physical and chemical stability in hydrogen atmosphere. In the case of the Li$$_{2+x}$$TiO$$_{3+y}$$ samples used by the present study, LiOHH$$_{2}$$O and H$$_{2}$$TiO$$_{3}$$ were proportionally mixed with the molar ratio Li/Ti of either 2.0 and 2.2. These samples are designated as L20 (Li/Ti = 2.0) and L22 (Li/Ti = 2.2), respectively. The results of XRD measurement showed that the phases in advanced tritium breeding material were as follows. L22 existed as non-stoichiometric compound Li$$_{2+x}$$TiO$$_{3+y}$$.

Journal Articles

Study of thermal stability for tertiary pyridine ion exchange resin and anti-corrosion property of structural material toward eluents used in the advanced ORIENT cycle process

Koyama, Shinichi; Ozawa, Masaki; Kurosawa, Kiyoko*; Tatenuma, Katsuyoshi*; Sato, Yoshihiko*; Okada, Ken*

Journal of Radioanalytical and Nuclear Chemistry, 286(3), p.807 - 813, 2010/12

 Times Cited Count:1 Percentile:11(Chemistry, Analytical)

A multi-functional separation process is proposed on the Adv.-ORIENT cycle concept. In this process, hydrochloric acid, mixture of nitric acid and methanol should be used as eluents. Two important subjects should be solved so as to prove the availability. One is corrosion aspect for the use of HCl solution, Tantalum was anti-corrosive in HCl media, and Hastelloy-B seemed to be acceptable at RT, with evidence of low corrosion rate ($$<$$ 0.1 mm/y). The other is explication of the reactive safety between ion exchange resin and solvent (nitric acid and methanol). The reaction occurred regardless of nitric acid concentration and presence or absence of methanol when the temperature of heater reached 220 $$^{circ}$$C. However, it was confirmed that the reaction did not occur when the heating temperature decreased.

Journal Articles

Trial fabrication of beryllide using plasma sintering method

Nakamichi, Masaru; Shibayama, Tamaki*; Tatenuma, Katsuyoshi*; Yonehara, Kazuo

Proceedings of 9th IEA International Workshop on Beryllium Technology (BeWS-9), p.40 - 43, 2009/09

Journal Articles

Adv.-ORIENT cycle; Its scientific progress and the engineering feasibility

Ozawa, Masaki; Suzuki, Tatsuya*; Koyama, Shinichi; Yamagishi, Isao; Fujita, Reiko*; Okada, Ken*; Tatenuma, Katsuyoshi*; Mimura, Hitoshi*; Fujii, Yasuhiko*

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.1117 - 1126, 2009/09

JAEA Reports

Study on $$^{99}$$Mo production by Mo-solution irradiation method, 3; Activation analysis of irradiation target

Huynh, T. P.*; Inaba, Yoshitomo; Ishida, Takuya; Ishikawa, Koji*; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Technology 2009-039, 21 Pages, 2009/07

JAEA-Technology-2009-039.pdf:2.53MB

The impurity concentration in both (NH$$_{4}$$)$$_{6}$$Mo$$_{7}$$O$$_{24}$$ and K$$_{2}$$MoO$$_{4}$$ solutions, which are selected as advanced targets of Mo-solution irradiation method for $$^{99}$$Mo production, was determined by the Instrumental Neutron Activation Analysis (NAA) using k$$_{0}$$-standardization method. As a result, Na, Mn and W were identified as impurities in the as received molybdate. After the compatibility test with structural material (SUS304) under $$gamma$$-ray irradiation, activation analysis of molybdate solutions was also carried out. It was found that the identified impurity concentration was stably staying in solutions and no element comes from the structural material by the NAA method. However, small corrosion of structural material was observed from the ICP measurement.

Journal Articles

New synthesis method of advanced lithium titanate with Li$$_{4}$$TiO$$_{4}$$ additives for ITER-TBM

Hoshino, Tsuyoshi; Kato, Kenichi*; Natori, Yuri*; Nakamura, Mutsumi*; Sasaki, Kazuya*; Hayashi, Kimio; Terai, Takayuki*; Tatenuma, Katsuyoshi*

Fusion Engineering and Design, 84(2-6), p.956 - 959, 2009/06

 Times Cited Count:39 Percentile:93.81(Nuclear Science & Technology)

Li$$_{2}$$TiO$$_{3}$$ is one of the most promising candidates among the proposed solid breeder materials for fusion reactors. Addition of H$$_{2}$$ to inert sweep gas has been proposed for enhancing the release of bred tritium from breeder material. However, the mass of Li$$_{2}$$TiO$$_{3}$$ was found to decrease with time in the hydrogen atmosphere. This mass change indicates that the oxygen content of the sample decreased, suggesting the change from Ti$$^{4+}$$ to Ti$$^{3+}$$. In order to control the mass change at the time of high temperature use, the development of lithium titanate which has Li$$_{4}$$TiO$$_{4}$$ additive is expected to be effective.

Journal Articles

Development on $$^{99}$$Mo production technique by solution irradiation method; Characterization of aqueous molybdate solutions

Inaba, Yoshitomo; Ishikawa, Koji*; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(2), p.142 - 153, 2009/06

A solution irradiation method is proposed as a new production technique of $$^{99}$$Mo, which is the parent nuclide of $$^{99m}$$Tc used as a radiopharmaceutical. In this new method, an aqueous molybdenum solution is irradiated with neutron in a nuclear reactor, and efficient and low cost $$^{99}$$Mo production comparing with conventional $$^{99}$$Mo production methods can be realized by using the $$^{98}$$Mo (n,$$gamma$$) $$^{99}$$Mo reaction and a high performance adsorbent for (n,$$gamma$$) $$^{99}$$Mo. In the present research, some tests under unirradiation and $$gamma$$-ray irradiation were carried out using two kinds of aqueous molybdate solutions to be candidates for the irradiation target of the new method, and the corrosivity for structural materials, chemical stability, radiolysis and $$gamma$$ heating of the solutions were investigated. As a result, it was found that the solutions are promising as the target and that stainless steel can be used as the structural material of capsules and pipes.

JAEA Reports

Study on $$^{99}$$Mo production by solution irradiation method, 2; Characterization of aqueous molybdate solutions under $$gamma$$-ray irradiation

Inaba, Yoshitomo; Ishikawa, Koji*; Iimura, Koichi; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Technology 2009-013, 72 Pages, 2009/05

JAEA-Technology-2009-013.pdf:32.51MB

In the present study, using two kinds of aqueous molybdate solutions (an aqueous ammonium molybdate solution and an aqueous potassium molybdate solution) selected as candidates for the irradiation target of the solution irradiation method for $$^{99}$$Mo production, the compatibility between the solutions and structural materials, the chemical stability, circulation characteristics, radiolysis and $$gamma$$ heating of the solutions were investigated under $$gamma$$-ray irradiation. In addition, the integrity of PZC was investigated under $$gamma$$-ray irradiation. As a result, the following were found: (1) the compatibility between the solutions and stainless steel is very well, (2) the solutions are chemically stable and have a smooth circulation, (3) the ratios of hydrogen in the gases generated by the radiolysis of the solutions are higher than that of pure water, (4) the effect of $$gamma$$ heating on the solutions is the same level as that on pure water, and (5) the integrity of PZC is maintained.

JAEA Reports

Study on $$^{99}$$Mo production by solution irradiation method, 1; Characterization of aqueous molybdate solutions under unirradiation

Inaba, Yoshitomo; Ishikawa, Koji*; Iimura, Koichi; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Technology 2009-012, 80 Pages, 2009/05

JAEA-Technology-2009-012.pdf:37.29MB

In the present study, the schematic structure of the $$^{99}$$Mo production system with the solution irradiation method was investigated, and two kinds of aqueous molybdate solutions (an aqueous ammonium molybdate solution and an aqueous potassium molybdate solution) were selected as candidates for the irradiation target of the solution irradiation method, and then the molybdenum adsorption performance of PZC with the solutions, the properties of the molybdates to be materials of the solutions, the compatibility between the solutions and structural materials, and the chemical stability of the solutions were investigated under unirradiation. As a result, it was found that the aqueous potassium molybdate solution is promising as the target in terms of the molybdenum content, the compatibility with the structural materials, and the chemical stability and that the aqueous ammonium molybdate solution with suitable pH adjustment has an aptitude for the target. In addition, it became clear that stainless steel having good compatibility with the solutions has a potential as the structural material of capsules, pipes and so on.

Journal Articles

Preliminary test for reprocessing technology development of tritium breeders

Hoshino, Tsuyoshi; Tsuchiya, Kunihiko; Hayashi, Kimio; Nakamura, Mutsumi*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*

Journal of Nuclear Materials, 386-388, p.1107 - 1110, 2009/04

 Times Cited Count:9 Percentile:56.98(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development on $$^{99}$$Mo production technology by molybdenum solution irradiation method

Inaba, Yoshitomo; Ishikawa, Koji*; Ishida, Takuya; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Conf 2008-010, p.259 - 267, 2008/12

$$^{99m}$$Tc for the medical diagnosis is the most widely used radioisotope in the world and it's demand is growing up year by year. In case of Japan, all $$^{99}$$Mo which is parent nuclide of $$^{99m}$$Tc, is imported. However, the importance of the domestic production is pointed out from a viewpoint of the stable supply of $$^{99}$$Mo because of some troubles on transportation or the research reactor, and so on. Therefore, the (n,$$gamma$$) method using solid molybdenum target had been planned in JMTR. However, it will be difficult to satisfy domestic demand because of the limited irradiation volumes of the hydraulic rabbit irradiation facility. In order to increase the amount of $$^{99}$$Mo production, the molybdenum solution irradiation method was proposed as a new production method. This method is based on the neutron irradiation of molybdenum solution, and several advantages can be pointed out such as a large irradiation volume, high efficient and low cost comparing with conventional methods using enriched $$^{235}$$U(n,f)$$^{99}$$Mo as the major method or using a solid molybdenum target of MoO$$_{3}$$ as the minor (n,$$gamma$$) method. Aiming at the realization of the molybdenum solution irradiation method, un-irradiated and $$gamma$$ ray irradiated tests of the molybdenum solution were carried out, and the data of chemical stability and compatibility with the structural materials were shown.

Journal Articles

Application of PZC to $$^{188}$$W/$$^{188}$$Re generators

Matsuoka, Hiromitsu; Hashimoto, Kazuyuki; Hishinuma, Yukio*; Ishikawa, Koji*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*; Uchida, Shoji*

Journal of Nuclear and Radiochemical Sciences, 6(3), p.189 - 191, 2005/12

Applicability of Mo adsorbent PZC(Poly Zirconium Compound) for $$^{188}$$W/$$^{188}$$Re generator was investigated. Long term stability of adsorption of $$^{188}$$W to the PZC column, elution of $$^{188}$$Re from PZC column, desorption of $$^{188W}$$ from PZC column, and labeling of Hydroxyethylidene Diphosphonic Acid(HEDP) and Mercaptoacetyltriglycine(MAG3) with $$^{188}$$Re eluted from PZC column were tested. The PZC generator gave reproducible $$^{188}$$Re elution yields with low $$^{188}$$W parent breakthrough for a long period of time(about 5 months), that is the $$^{188}$$W/$$^{188}$$Re generator using PZC has a potential for practical use.

Oral presentation

Application of PZC to $$^{188}$$W/$$^{188}$$Re generator

Hashimoto, Kazuyuki; Hishinuma, Yukio*; Ishikawa, Koji*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*; Uchida, Shoji*; Matsuoka, Hiromitsu

no journal, , 

Applicability of Mo adsorbent PZC(Poly Zirconium Compound) for $$^{188}$$W/$$^{188}$$Re generator was investigated. Up to the present, long term stability of adsorption of $$^{188}$$W to the PZC column, elution of $$^{188}$$Re from PZC column, desorption of $$^{188}$$W from PZC column, and labeling of Hydroxyethylidene Diphosphonic Acid (HEDP) and Mercaptoacetyltriglycine (MAG3) with $$^{188}$$Re eluted from PZC column were tested and the results were compared with that of $$^{188}$$Re eluted from alumina column.

Oral presentation

Development of Li resource recycle technology for tritium breeding materials

Terunuma, Hitoshi*; Nakamura, Mutsumi*; Tatenuma, Katsuyoshi*; Tsuchiya, Kunihiko; Hoshino, Tsuyoshi; Hayashi, Kimio

no journal, , 

no abstracts in English

Oral presentation

Study on $$^{99}$$Mo production method with irradiation of circulating Mo solution, 1; Results of cold tests (preliminary tests)

Inaba, Yoshitomo; Ishikawa, Koji*; Ishida, Takuya; Ishitsuka, Etsuo; Kurosawa, Kiyoko*; Hishinuma, Yukio*; Tatenuma, Katsuyoshi*

no journal, , 

The circulating solution irradiation method is a new production method of $$^{99}$$Mo, which is the parent nuclide of $$^{99m}$$Tc used as medical diagnosis medicine. In order to realize this method, compatibility between molybdenum solutions and structural materials, etc. were investigated. As a result, it was found that the potassium molybdate solution have good characteristics as an irradiation target.

Oral presentation

Development of Li resource recycle technology for tritium breeding materials in Broader Approach

Hoshino, Tsuyoshi; Hayashi, Kimio; Nakamura, Mutsumi*; Nemoto, Tadahiro*; Tatenuma, Katsuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of mass production technology of advanced solid breeder material for ITER-TBM

Hoshino, Tsuyoshi; Nemoto, Tadahiro*; Nakamura, Mutsumi*; Suzuki, Akihiro*; Hayashi, Kimio; Tatenuma, Katsuyoshi*; Terai, Takayuki*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of anti-corrosion materials for tertiary pyridine resine-based reprocessing, 3; The First screening of anti-corrosion materials for a novel reprocessing system

Ozawa, Masaki; Koyama, Shinichi; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Fujii, Yasuhiko*

no journal, , 

no abstracts in English

31 (Records 1-20 displayed on this page)