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JAEA Reports

Experimental and numerical study on energy separation in vortex tube with a hollow helical fin (Joint research)

Kureta, Masatoshi; Yamagata, Yoji*; Miyakoshi, Ken*; Mashii, Tatsuya*; Miura, Yoshiaki*; Takahashi, Kazunori*

JAEA-Research 2022-007, 28 Pages, 2022/09

JAEA-Research-2022-007.pdf:8.17MB

To enhance energy separation in a counter-current Ranque-Hilsch vortex tube, a newly designed hollow helical fin was inserted into the hot tube of the vortex tube. In this study, the effect of the fin on the energy separation was investigated using three types of the vortex tube, and then computational fluid dynamics (CFD) simulation has been conducted to understand the experimental results and discuss the flow structure in the vortex tube with the hollow helical fin. As a result, it was found from the experimental data that the fin effectively enhanced energy separation, and that the tube length could be shorten. When the inlet air pressure was 0.5 MPa, the maximum temperature difference from the inlet to the cold exit was 62.2$$^{circ}$$C. The CFD code employing the Reynolds Stress Model (RSM) turbulence model was used to analyze the fluid dynamics in the vortex tube. As a result, it was confirmed that the temperature, velocity, and pressure distributions changed significantly at the stagnation point, and that the distributions in the tube with the fin were completely different from those without the fin. It was thought that a strong reversing helical vortex flow with small recirculating vortex structure formed between the fin end and the stagnation point on the cold exit side would enhance energy separation in the vortex tube with the hollow helical fin.

JAEA Reports

Development of fundamental technologies for domestic production of medical radioisotope (technetium-99m); The First and second phase report (FY2014-2020)

Project 6 Meeting Members for Tsukuba International Strategic Zone

JAEA-Review 2021-016, 102 Pages, 2021/11

JAEA-Review-2021-016.pdf:12.76MB

In December 2011, the Prime Minister designated Tsukuba and some areas in Ibaraki Prefecture as "Comprehensive Special Zones". In the Tsukuba International Strategic Zone, nine advanced research and development (R&D) projects are underway with the goal of promoting industrialization of life innovation and green innovation utilizing the science and technology in Tsukuba. In these projects, the domestic production of medical radioisotope (Technetium-99m, $$^{rm 99m}$$Tc) was certified as a new project in October 2013, and R&D have been performed in collaboration with related organizations with Japan Atomic Energy Agency (JAEA) as the project leader. Japan is the third largest consumer of molybdenum-99 ($$^{99}$$Mo) after the United States and Europe, and all $$^{99}$$Mo are imported. Supply will be insufficient if overseas reactors are shut down due to trouble or if transportation (air and land transportations) is stopped due to volcanic eruptions and some accidents. Thus, early domestic production of $$^{99}$$Mo is strongly required. This project is a technology development aimed at domestic production of $$^{99}$$Mo, which is a raw material of $$^{rm 99m}$$Tc used as a diagnostic agent. This report summarizes the activities carried out in the first and second phase of the domestic production of medical radioisotope ($$^{rm 99m}$$Tc) (here referred to as the "Project 6") in Tsukuba International Strategic Zone (FY2014-2020).

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

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

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

Oral presentation

Applicability of metal boride hardness measurement using Laser-Induced Breakdown Spectroscopy (LIBS), 1; Simultaneous measuring of elemental composition information and hardness

Makuuchi, Etsuyo*; Nagayama, Sakiko*; Abe, Yuta; Okazaki, Kodai*; Kawakami, Tomohiko*; Oishi, Yuji*; Otaka, Masahiko

no journal, , 

no abstracts in English

Oral presentation

Applicability of metal boride hardness measurement using Laser-Induced Breakdown Spectroscopy (LIBS), 2; Element distribution of metal boride specimens with complicated composition

Okazaki, Kodai*; Kawakami, Tomohiko*; Nagayama, Sakiko*; Abe, Yuta; Otaka, Masahiko; Makuuchi, Etsuyo*; Oishi, Yuji*; Takagai, Yoshitaka*

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)