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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.

Oral presentation

Development of irradiation technology for restart of JMTR, 2; Recycling of molybdenum from $$^{99m}$$Tc generators and reducing of radioactive waste

Yoshinaga, Hideo*; Kakei, Sadanori*; Tanimoto, Masataka; Kimura, Akihiro; Tsuchiya, Kunihiko

no journal, , 

JP, 2010-152220   Patent publication (In Japanese)

no abstracts in English

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

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

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

no journal, , 

Every year in Japan, nuclear medical of about 900,000 cases are carried out using technetiume-99m ($$^{99m}$$Tc). It is ranked as the second in the world. But all of the $$^{99m}$$Tc is imported from the other countries. Therefore, we are developing the (n, $$gamma$$) method for $$^{99}$$Mo production, as part of "increase of industrial use" in resumed operations after restart of Japan Materials Tasting Reactor (JMTR). In the study to establish the $$^{99}$$Mo production method through the (n, $$gamma$$) process domestically using the JMTR, three different MoO$$_{3}$$ powders such as fresh, recycled and $$^{98}$$Mo enriched ones were selected, and characterized as in SEM and sintering. As a result, the high dense MoO$$_{3}$$ pellet manufactured by the fresh powder attained over 90%T. D. at the sintering temperature of 500$$^{circ}$$C. On the other hand, pellets manufactured by the other powders needs sintering temperature above 580$$^{circ}$$C to attain over 90%T.D., resulting in an influence on the particle size and shape dependences for the sintering property.

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

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

Molybdenum adsorption and recovery properties of alumina adsorbent for $$^{99}$$Mo/$$^{99m}$$Tc generator

Suzuki, Yoshitaka; Namekawa, Yoji*; Kitagawa, Tomoya*; Kakei, Sadanori*; Matsukura, Minoru*; Yoshinaga, Hideo*; Mimura, Hitoshi*; 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

Patent

テクネチウム99Mジェネレータからのモリブデン回収方法

谷本 政隆; 木村 明博; 土谷 邦彦

吉永 英雄*; 掛井 貞紀*

JP, 2010-152220  Patent licensing information  Patent publication (In Japanese)

【課題】使用済テクネチウム99mジェネレータから、モリブデンを、簡便な溶離法により回収でき、かつ、再利用し易いモリブデン酸の形状で入手すること、さらには放射性廃棄物を減容すること。 【解決手段】PZCから成るモリブデン含有の使用済テクネチウム99mジェネレータに、1Nから4Nのアルカリ濃度を持つアルカリ溶液を一定時間にわたって徐々に加え、モリブデン含有アルカリ溶液を取り出し、該溶液を加熱した後、酸を加えて強酸性に調整し、一定時間放冷して、モリブデンをモリブデン酸として回収する。また、このモリブデン回収方法を複数回繰り返したテクネチウム99mジェネレータを700℃以上で加熱し、含まれているモリブデンを昇華させ、モリブデンを三酸化モリブデンとして回収すると共に、PZCをジルコニアとして回収する。

Patent

モリブデンのサイクルシステム及び当該サイクルシステムに使用されるモリブデン吸着剤の再生方法

谷本 政隆; 木村 明博; 西方 香緒里; 土谷 邦彦

長谷川 良雄*; 菱沼 行男*; 新関 智丈*; 鈴木 将*; 永山 紗智子*; 吉永 英雄*; 掛井 貞紀*

JP, 2012-081241  Patent licensing information  Patent publication (In Japanese)

【課題】モリブデンの効率的な回収を低コストで行うためのモリブデンのサイクルシステム及び該サイクルシステムに使用されるモリブデン吸着剤の再生方法を提供する。 【解決手段】本発明は、モリブデン99を含有するモリブデン又は三酸化モリブデンを溶解してモリブデン吸着剤に吸着する工程、前記のモリブデン吸着剤から成るジェネレータからテクネチウム99Mを抽出した後の使用済みモリブデン吸着剤に存在するモリブデンを脱着する工程、前記モリブデン脱着後のモリブデン吸着剤にモリブデン99含有のモリブデンを再吸着する工程、及び前記の脱着工程によって回収される三酸化モリブデンを再利用する工程を含むモリブデンのサイクルシステムであり、前記の再吸着工程で使用されるモリブデン脱着後の再生モリブデン吸着剤は、水中等で保存され、繰返し単位の構造中にOH基を少なくとも1つ有することを特徴とする。

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