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JAEA Reports

Preliminary test for Mo recycling system in $$^{99}$$Mo manufacturing process, 1; Reusability evaluation of Mo absorbent (Joint research)

Kimura, Akihiro; Niizeki, Tomotake*; Kakei, Sadanori*; Chakrova, Y.*; Nishikata, Kaori; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Chakrov, P.*; Tsuchiya, Kunihiko

JAEA-Technology 2013-025, 40 Pages, 2013/10

JAEA-Technology-2013-025.pdf:2.62MB

Neutron Irradiation and Testing Reactor Center has developed the production of a medical isotope of $$^{99}$$Mo, the parent nuclide of $$^{99m}$$Tc by the (n,$$gamma$$) method using JMTR. The (n,$$gamma$$) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of $$^{99m}$$Tc is remaining as an issue. Therefore, PZC and PTC have been developed as adsorbent of molybdenum. Meanwhile, it is necessary to recycle the absorbent and Mo for the reduction of the radioactive waste of used-adsorbent and the effective use of limited resources, respectively. This report summarizes results of the synthesis of Mo adsorbents such as PZC and PTC, and the performance tests.

Journal Articles

Mo recycling property from generator materials with irradiated molybdenum

Kakei, Sadanori*; Kimura, Akihiro; Niizeki, Tomotake*; Ishida, Takuya; Nishikata, Kaori; Kurosawa, Makoto; Yoshinaga, Hideo*; Hasegawa, Yoshio*; Tsuchiya, Kunihiko

Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 7 Pages, 2013/10

The Japan Materials Testing Reactor (JMTR) is expected to contribute to the expansion of industrial utilization, such as the domestic production of $$^{99}$$Mo for the medical diagnosis medicine $$^{rm 99m}$$Tc. Production by the (n, $$gamma$$) method is proposed as domestic $$^{99}$$Mo production in JMTR because of the low amount of radioactive wastes and the easy $$^{99}$$Mo/$$^{rm 99m}$$Tc production process. Molybdenum oxide (MoO$$_{3}$$) pellets, poly zirconium compounds (PZC) and poly titanium compounds (PTC) are used as the irradiation target and generator for the production of $$^{99}$$Mo/$$^{rm 99m}$$Tc by the (n, $$gamma$$) method. However, it is necessary to use the enriched $$^{98}$$MoO$$_{3}$$, which is very expensive, to increase the specific activity of $$^{99}$$Mo. Additionally, a large amount of used PZC and PTC is generated after the decay of $$^{99}$$Mo. Therefore, this recycling technology of used PZC/PTC has been developed to recover molybdenum (Mo) as an effective use of resources and a reduction of radioactive wastes. The total Mo recovery rate of this process was 95.8%. From the results of the hot experiments, we could demonstrate that the recovery of MoO$$_{3}$$ and the recycling of PZC are possible. In the future, the equipment of recovering Mo will be installed in JMTR-Hot Cell, and this recycling process will be able to contribute to the reduction of production costs of $$^{rm 99m}$$Tc and the reduction of radioactive wastes.

Journal Articles

Development of $$^{99}$$Mo-$$^{rm 99m}$$Tc domestic production with high-density MoO$$_{3}$$ pellets by (n,$$gamma$$) reaction

Tsuchiya, Kunihiko; Tanase, Masakazu*; Takeuchi, Nobuhiro*; Kobayashi, Masaaki*; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi

Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 10 Pages, 2012/10

As one of effective uses of the JMTR, JAEA has a plan to produce $$^{99}$$Mo by (n, $$gamma$$) method, a parent nuclide of $$^{rm 99m}$$Tc. In case of Japan, the supplying of $$^{99}$$Mo depends only on imports from foreign countries. The R&D on production method of $$^{99}$$Mo -$$^{rm 99m}$$Tc has been performed with Japanese industrial users under the cooperation programs. The main R&D items for the production are (1) Fabrication of irradiation target such as the sintered MoO$$_{3}$$ pellets, (2) Separation and concentration of $$^{rm 99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{rm 99m}$$Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this paper, the status of the R&D is introduced for the production of $$^{99}$$Mo -$$^{rm 99m}$$Tc.

JAEA Reports

Photocatalytic activity of Sulfur-doped TiO$$_{2}$$ fiber under visible light illumination (Joint research)

Takeyama, Akinori; Yamamoto, Shunya; Yoshikawa, Masahito; Hasegawa, Yoshio*; Awatsu, Satoshi*

JAEA-Research 2007-012, 29 Pages, 2007/03

JAEA-Research-2007-012.pdf:3.77MB

The Sol-Gel derived precursor fiber was annealed under hydrogen disulfeid (H$$_{2}$$S) following oxygen atmosphere, Sulfer-doped titanium dioxide (TiO$$_{2}$$) fiber was obtained. Crystal structure of the fiber was identified as anatase phase of TiO$$_{2}$$. The energy band gap of the fiber was narrower by about 0.06 eV than that of anatase, which showed that it could absorb visible light. The fiber contains about 0.58 atomic % of Sulfer, and they located at the oxygen lattice site of TiO$$_{2}$$. Under visible light illumination, the fiber degraded Trichroloethylen (TCE) and produced carbon dioxide (CO$$_{2}$$). This shows Sulfer-doped TiO$$_{2}$$ fiber has the photocatalytic activity under visible light illumination.

Oral presentation

Effect on sintering property of MoO$$_{3}$$ pellets of different MoO$$_{3}$$ powders

Nishikata, Kaori; Kimura, Akihiro; Kato, Yoshiaki; Kurosawa, Makoto; Ishida, Takuya; Tsuchiya, Kunihiko; Kakei, Sadanori*; Yoshinaga, Hideo*; Niizeki, Tomotake*; Hasegawa, Yoshio*

no journal, , 

no abstracts in English

Oral presentation

Fabrication technique development of high-density MoO $$_{3}$$ pellets for $$^{99}$$Mo/ $$^{99m}$$Tc production

Nishikata, Kaori; Kimura, Akihiro; Kato, Yoshiaki; Kurosawa, Makoto; Ishida, Takuya; Tsuchiya, Kunihiko; Kakei, Sadanori*; Yoshinaga, Hideo*; Niizeki, Tomotake*; Hasegawa, Yoshio*

no journal, , 

no abstracts in English

Oral presentation

Sorption characteristics of ceramics nanosheets for platinum-group substances in high-level radioactive liquid waste, 1; Fundamental study on trial production and selection of nanosheets

Amamoto, Ippei; Yokozawa, Takuma; Kobayashi, Hidekazu; Taguchi, Tomitsugu; Hasegawa, Yoshio*; Hishinuma, Yukio*; Yamakawa, Atsushi*

no journal, , 

no abstracts in English

Oral presentation

Sorption characteristics of ceramics nanosheets for platinum-group substances in high-level radioactive liquid waste

Hasegawa, Yoshio*; Hishinuma, Yukio*; Amamoto, Ippei; Yokozawa, Takuma; Kobayashi, Hidekazu; Taguchi, Tomitsugu; Yamakawa, Atsushi*; Suzuki, Masashi*

no journal, , 

no abstracts in English

Oral presentation

Sorption characteristics of ceramics nanosheets for platinum-group substances in high-level radioactive liquid waste, 2; Manufacture of nanosheets and their sorption behaviour

Yamakawa, Atsushi*; Amamoto, Ippei; Yokozawa, Takuma; Kobayashi, Hidekazu; Taguchi, Tomitsugu; Hasegawa, Yoshio*; Hishinuma, Yukio*

no journal, , 

no abstracts in English

Oral presentation

Status of $$^{99}$$Mo/$$^{99m}$$Tc production development by (n,$$gamma$$) reaction in JMTR

Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori

no journal, , 

Technetium-99m ($$^{99m}$$Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce $$^{99}$$Mo by (n,$$gamma$$) method, a parent nuclide of $$^{99m}$$Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of $$^{99}$$Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of $$^{99}$$Mo/$$^{99m}$$Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on $$^{99}$$Mo/$$^{99m}$$Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of $$^{99m}$$Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO$$_{3}$$ pellets, (2) Separation and concentration of $$^{99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{99m}$$Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of $$^{99}$$Mo/$$^{99m}$$Tc production improvement.

Oral presentation

Development on the inorganic porous materials to sorb platinoid elements

Amamoto, Ippei; Kobayashi, Hidekazu; Ayame, Yasuo; Utsumi, Kazuo*; Takeshita, Kenji*; Onoe, Jun*; Nagayama, Sachiko*; Hasegawa, Yoshio*

no journal, , 

no abstracts in English

Oral presentation

Research and development of $$^{99}$$Mo/$$^{99m}$$Tc production process by (n,$$gamma$$) reaction under Tsukuba International Strategic Zones

Tsuchiya, Kunihiko; Kawamata, Kazuo; Takeuchi, Nobuhiro*; Ishizaki, Hiroyuki*; Niizeki, Tomotake*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Araki, Masanori

no journal, , 

no abstracts in English

Oral presentation

Consideration of molybdenum adsorption behavior of alumina by surface analysis

Suzuki, Yoshitaka; Niizeki, Tomotake*; Kitagawa, Tomoya*; Nishikata, Kaori; Matsukura, Minoru*; Hasegawa, Yoshio*; Tanase, Masakazu*; Fukumitsu, Nobuyoshi*; Yamauchi, Yusuke*; Ariga, Katsuhiko*; et al.

no journal, , 

no abstracts in English

Oral presentation

Domestic production of medical radioisotope (technetium-99m)

Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Research and development of $$^{99}$$Mo/$$^{99m}$$Tc production process by (n,$$gamma$$) method

Tsuchiya, Kunihiko; Shibata, Tokushi*; Uno, Tsuyoshi*; Hasegawa, Yoshio*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Kusunoki, Tsuyoshi; Kaminaga, Masanori

no journal, , 

no abstracts in English

15 (Records 1-15 displayed on this page)
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