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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, 
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 (
Mo) after the United States and Europe, and all 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 Mo is strongly required. This project is a technology development aimed at domestic production of Mo, which is a raw material of 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 (Tc) (here referred to as the "Project 6") in Tsukuba International Strategic Zone (FY2014-2020).
Mo/
Tc production by neutron activation methodIshida, Takuya; Shiina, Takayuki*; Ota, Akio*; Kimura, Akihiro; Nishikata, Kaori; Shibata, Akira; Tanase, Masakazu*; Kobayashi, Masaaki*; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
JAEA-Technology 2015-030, 42 Pages, 2015/11
JAEA-Technology-2015-030.pdf:4.82MB
The research and development (R&D) on the production of Mo/Tc by neutron activation method ((n, 
) method) using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center. The specific radioactivity of Mo by (n, ) method is extremely low compared with that by fission method ((n,f) method), and as a result, the radioactive concentration of the obtained Tc solution is also lowered. To solve the problem, we propose the solvent extraction with methyl ethyl ketone (MEK) for recovery of Tc from Mo produced by (n, ) method. We have developed the Mo/Tc separation/extraction/concentration devices and have carried out the performance tests for recovery of Tc from Mo produced by (n, ) method. In this paper, in order to establish an experimental system for Mo/Tc production, the R&D results of the system are summarized on the improvement of the devices for high-recovery rate of Tc, on the dissolution of the pellets, which is the high-density molybdenum trioxide (MoO
) pellets irradiated in Kyoto University Research Reactor (KUR), on the production of Tc, and on the inspection of the recovered Tc solutions.
Mo adsorption and Tc elution from zirconium-based material in Mo/Tc generator column using neutron-irradiated natural molybdenumAwaludin, R.*; Gunawan, A. H.*; Lubis, H.*; Sriyono*; Herlina*; Mutalib, A.*; Kimura, Akihiro; Tsuchiya, Kunihiko; Tanase, Masakazu*; Ishihara, Masahiro
Journal of Radioanalytical and Nuclear Chemistry, 303(2), p.1481 - 1483, 2015/02
Times Cited Count：9 Percentile：56.39(Chemistry, Analytical)In this study, the Mo adsorption and Tc elution mechanism were investigated using SEM-EDS to analyze the elemental composition of the material surfaces before Mo adsorption, after Mo adsorption and after Tc elution using saline solution. The results were compared with the value of adsorption capacity of the material to irradiated natural Mo and elution yield of Tc. From the changes of elemental composition in the surface, it was found that molybdate ions were adsorbed into the adsorbent by ion exchange with Cl
ion in the material. On the other hand, it was also revealed that Tc can be eluted from the material column in TcO
since oxidizing agent was needed in the elution process.
Mo/Tc production by (n,) methodNishikata, Kaori; Kimura, Akihiro; Ishida, Takuya; Shiina, Takayuki*; Ota, Akio*; Tanase, Masakazu*; Tsuchiya, Kunihiko
JAEA-Technology 2014-034, 34 Pages, 2014/10
JAEA-Technology-2014-034.pdf:3.26MB
As a part of utilization expansion after the Japan Material Testing Reactor (JMTR) re-start, research and development (R&D) on the production of medical radioisotope Mo/Tc by (n, ) method using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center of the Japan Atomic Energy Agency. Mo is usually produced by fission method. On the other hand, Mo/Tc production by the (n, ) method has advantages for radioactive waste, cost reduction and non-proliferation. However, the specific radioactivity per unit volume by the (n, ) method is low compared with the fission method, and that is the weak point of the (n, ) method. This report summarizes the investigation of raw materials, the fabrication tests of high-density MoO pellets by the plasma sintering method for increasing of 
Mo contents and the characterization of sintered high-density MoO pellets.
Lu and 
Re, 
Re using a research reactorHashimoto, Kazuyuki; Fujisaki, Saburo*
Hoshasen To Sangyo, (136), p.17 - 21, 2014/06
no abstracts in English
Tc production from (n,)Mo based on solvent extractionKimura, Akihiro; Awaludin, R.*; Shiina, Takayuki*; Tanase, Masakazu*; Kawauchi, Yukimasa*; Gunawan, A. H.*; Lubis, H.*; Sriyono*; Ota, Akio*; Genka, Tsuguo; et al.
Proceedings of 3rd Asian Symposium on Material Testing Reactors (ASMTR 2013), p.109 - 115, 2013/11
JP, 2011-173260 Patent publication (In Japanese)
Tc is generated by decay of Mo. Production of Mo is carried out by (n,f) method with high enriched uranium targets, and the production are currently producing to meet about 95% of global supply. Recently, it is difficult to carry out a stable supply for some problems such as aging of reactors etc. Furthermore, the production has difficulties in nuclear proliferation resistance etc. Thus, (n,) method has lately attracted considerable attention. The (n,) method has several advantages, but the extremely low specific activity makes its uses less convenient than (n,f) method. We proposed a method based on the solvent extraction, followed by adsorption of Tc with alumina column. In this paper, a practical production of Tc was tried by the method with 1Ci of Mo produced in MPR-30. The recovery yields were approximately 70%. Impurity of Mo was less than 4.0
10
% and the radiochemical purity was over 99.2%.
Hiroki, Akihiro; Sato, Yuichi*; Nagasawa, Naotsugu; Ota, Akio*; Seito, Hajime; Yamabayashi, Hisamichi*; Yamamoto, Takayoshi*; Taguchi, Mitsumasa; Tamada, Masao; Kojima, Takuji
Physics in Medicine & Biology, 58(20), p.7131 - 7141, 2013/10
Times Cited Count：20 Percentile：57.94(Engineering, Biomedical)Mo-Tc production process by (n,) reaction with irradiated high-density MoO pelletsTsuchiya, Kunihiko; Nishikata, Kaori; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kobayashi, Masaaki*; Yamamoto, Asaki*; Morikawa, Yasumasa*; Takeuchi, Nobuhiro*; Kaminaga, Masanori; et al.
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 9 Pages, 2013/10
no abstracts in English
Tc production from (n,)Mo based on solvent extraction and column chromatographyKimura, Akihiro; Awaludin, R.*; Shiina, Takayuki*; Tanase, Masakazu*; Kawauchi, Yukimasa*; Gunawan, A. H.*; Lubis, H.*; Sriyono*; Ota, Akio*; Genka, Tsuguo; et al.
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 7 Pages, 2013/10
JP, 2011-173260Patent publication (In Japanese)
This research is development of Tc production. Tc is generated by decay of Mo. The supply of Mo in Japan depends entirely on the import from foreign countries. Thus, it is needed to supply Mo stably by the domestic manufacturing. A practical production of Tc was tried by the method with 1 Ci of Mo produced in MPR-30. The results showed that the recovery yields were approximately 70%. The concentration of the product obtained was estimated to be corresponding to about 30 GBq (800 mCi)/ml when 150g of MoO was irradiated for 5 days in MPR-30. Impurity of Mo was less than 4.410%, which was lower than that of Japanese tentative regulation criteria. The radiochemical purity was higher than 99.8% that cleared the tentative regulation (95%) of Japan.
Fujibuchi, Toshio*; Kawamura, Taku*; Yamanashi, Koichi*; Hiroki, Akihiro; Yamashita, Shinichi*; Taguchi, Mitsumasa; Sato, Yuichi*; Mimura, Koichi*; Ushiba, Hiroaki*; Okihara, Toru*
Journal of Physics; Conference Series, 444(1), p.012089_1 - 012089_4, 2013/06
Times Cited Count：4 Percentile：76.87(Physics, Multidisciplinary)Hiroki, Akihiro; Yamashita, Shinichi; Sato, Yuichi*; Nagasawa, Naotsugu; Taguchi, Mitsumasa
Journal of Physics; Conference Series, 444, p.012028_1 - 012028_4, 2013/06
Times Cited Count：10 Percentile：90.99(Physics, Multidisciplinary)Polymer gel dosimeters consisting of less toxic methacrylate-type monomers such as 2-hydroxyethyl methacrylate (HEMA) and polyethylene glycol 400 dimethacrylate (9G) with hydroxypropyl cellulose (HPC) gel were prepared. We investigated the effect of monomer compositions on the dose response of the polymer gel dosimeter. The HPC gels as a matrix for the polymer gel dosimeter were obtained by electron beam irradiation to 20wt% of HPC aqueous solution. The dried HPC gels were immersed into mixed monomer solutions, and then the swollen gels were vacuum-packed to prepare the polymer gel dosimeters. The polymer gel dosimeters showed cloudiness by exposing to 
Co -ray, in which the cloudiness increased with the dose up to 10 Gy. At the same dose, the increase in the cloudiness appeared with increasing concentration of 9G. It was found that the dose response depended on the composition ratio between HEMA and 9G.
pelletsNishikata, Kaori; Kimura, Akihiro; Shiina, Takayuki*; Ota, Akio*; Tanase, Masakazu*; Tsuchiya, Kunihiko
Proceedings of 2012 Powder Metallurgy World Congress & Exhibition (PM 2012) (CD-ROM), 8 Pages, 2013/02
The renewed Japan Materials Testing Reactor (JMTR) will be started from 2012, and it is expected to contribute to many nuclear fields. Especially, in case of Japan, the supplying of Mo depends on imports from foreign countries. Japan Atomic Energy Agency (JAEA) has a plan to produce Mo, which is the parent nuclide of radiopharmaceutical Tc, and JAEA has performed the R&D for Mo production by (n,) method in JMTR. Generally, molybdenum oxide (MoO) is the most popular chemical form as irradiation target for the Mo production. However, the Mo production capacity is low because of low (n,) cross section and isotope composition of Mo in Mo. Thus, it is necessary to fabricate the MoO pellets with high density for the increase of the Mo production amount. In this study, MoO pellets fabricated by a plasma activated sintering were developed and characterization of MoO pellets was carried out.
Mo/Tc; Development of Mo/Tc production using accelerator neutronsNagai, Yasuki
Radioisotopes, 61(12), p.619 - 624, 2012/12
A new method was proposed to produce Mo by the 
Mo(n,2n)Mo reaction using intense neutrons from an accelerator by us. About 20% of the demand of Mo in Japan could be obtained constantly by the proposed method. In fact, we have shown that the produced Mo contained very little RI impurity and the radionuclide purity of Tc separated from Mo by sublimation and the labeling efficiency of Tc-MDP exceed the United States Pharmacopeia requirements for a fission product, Mo. We expect that the present Mo production method will be accepted worldwide to ensure the constant domestic supply of Mo.
pellets for (n, ) Mo productionNishikata, Kaori; Kimura, Akihiro; Tsuchiya, Kunihiko; Suzuki, Kunihiko*; Akiyama, Hiroaki*; Nagakura, Masaaki*; Kawauchi, Yukimasa*; Tanase, Masakazu*
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10
In this study, experimental fabrication tests of the high-density MoO pellets were carried out by the Plasma Activated Sintering (PAS) method, which requires relatively lower temperature and shorter time to fabricate the pellets. From the results, the PAS method combined with oxidation process, prior to dissolution into sodium hydroxide solution, is a useful measure to fabricate high-density MoO Pellets for the future domestic production of Tc. The irradiation tests and characterization with these pellets will be carried out under the international cooperation.
Mo-Tc domestic production with high-density MoO pellets by (n,) reactionTsuchiya, 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 Mo by (n, ) method, a parent nuclide of Tc. In case of Japan, the supplying of Mo depends only on imports from foreign countries. The R&D on production method of Mo -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 pellets, (2) Separation and concentration of Tc by the solvent extraction from Mo solution, (3) Examination of 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 Mo -Tc.
Tc production from (n, ) MoTanase, Masakazu*; Shiina, Takayuki*; Kimura, Akihiro; Nishikata, Kaori; Fujisaki, Saburo*; Ota, Akio*; Kobayashi, Masaaki*; Yamamoto, Asaki*; Kawauchi, Yukimasa*; Tsuchiya, Kunihiko; et al.
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10
Tc is used as a radiopharmaceutical and manufactured from the parent nuclide of Mo. Extraction method of Tc from (n, ) Mo have been developed, as a part of the industrial use expansion after JMTR will re-start. In this research, the method proposed would be applicable to a practical production of Tc obtained from (n, ) Mo in large quantities. The method proposed would be applicable to a practical production of Tc obtained from (n, ) Mo in large quantities.
Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.
JAEA-Technology 2011-031, 123 Pages, 2012/01
JAEA-Technology-2011-031.pdf:16.08MB
The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.
Hashimoto, Kazuyuki
FBNews, (420), p.1 - 5, 2011/12
no abstracts in English
pellets for production of Mo medical isotopeKimura, Akihiro; Sato, Yuichi*; Tanase, Masakazu*; Tsuchiya, Kunihiko
IOP Conference Series; Materials Science and Engineering, 18(4), p.042001_1 - 042001_4, 2011/10
In the medical field, the radioisotopes are indispensable. Especially, Tc is most commonly used as a radiopharmaceutical. However, the supply of Mo in Japan depends fully on the import from foreign countries. JMTR has a plan to produce a medical isotope of Mo, the parent nuclide of Tc by the (n,) method and a part of the import volume can be covered of the home country. In this plan, it is important to develop the production method of the irradiation targets such as the Molybdenum oxide (MoO) pellets. However, MoO is low sublime temperature and it is difficult to produce the pellets with high density. In this study, MoO pellets were produced by two kinds of production methods. As a result, MoO pellet of about 70% TD was obtained by CIP and MoO pellet of over 95% TD was obtained by SPS.
Tc master-milker; Comparison with PZC based wet methodIshitsuka, Etsuo; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Norihito*; Hori, Naohiko; Awaludin, R.*; Gunawan, A. H.*; Lubis, H.*; Mutalib, A.*
JAEA-Technology 2011-019, 18 Pages, 2011/06
JAEA-Technology-2011-019.pdf:2.61MB
Feasibility study of sublimation type Tc master-milker was carried out as a Mo/T production development with the JMTR. As the feasibility study, the experimental equipment for sublimation method and wet method with PZC based Tc solution were tentatively manufactured, and their properties as the master-milker were investigated by comparing two methods with each other. As a result, it was found that the Tc recovery rate and process time of the sublimation method were about 80% and 1.5 hour, respectively, and the similar values were observed with the wet method. Superior points of the sublimation method are easier operation and reusability of the used MoO comparing with the wet method. On the other hand, disadvantageous point is that the Tc recovery rate decreases with the increase of treating amount of MoO.
