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Mo) adsorption profile of zirconia-based materials for Mo/
Tc generator applicationMarlina*; Lestari, E.*; Abidin*; Hambali*; Saptiama, I.*; Febriana, S.*; Kadarisman*; Awaludin, R.*; Tanase, Masakazu*; Nishikata, Kaori; et al.
Atom Indonesia, 46(2), p.91 - 97, 2020/08
Technetium-99m (Tc) plays a major role in diagnostic nuclear medicine and has not yet been replaced with any other radionuclides. It is available through the Mo/Tc generator. The use of low-specific-activity Mo for Mo/Tc generator application requires high adsorptive capacity sorbents. This study focused on the determination of Mo adsorption capacity of several zirconia materials, namely monoclinic nanozirconia, orthorhombic nanozirconia, sulfated zirconia, and phosphated zirconia. These materials were synthesized by using the sol-gel method and characterized using FT-IR spectroscopy, X-ray diffraction (XRD), and scanning electron microscopy/energy-dispersive X-ray spectroscopy (SEM-EDS). The determination of Mo adsorption capacity of these materials was carried out by soaking the materials in a Na
MoO
solution with pH of 3 and 7, at temperatures ranging from room temperature to 90 
C, for 1 and 3 hours. As a result, orthorhombic nano-zirconia was found to have the highest Mo adsorption performance and is considered to be a candidate material for Mo/Tc generator.
Tc solution from Mo to be obtained by (
) reaction; A Preliminary study using inactive Re instead of TcTanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*; Shiina, Takayuki*; Yamabayashi, Hisamichi*; Takeuchi, Nobuhiro*; Tsuchiya, Kunihiko; Kimura, Akihiro; Suzuki, Yoshitaka; Ishida, Takuya; et al.
Radioisotopes, 65(5), p.237 - 245, 2016/05
no abstracts in English
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.
Niwa, Masakazu; Mizuochi, Yukihiro*; Tanase, Atsushi*
Geofluids, 15(3), p.387 - 409, 2015/08
Times Cited Count：18 Percentile：60.88(Geochemistry & Geophysics)It is expected that in some cases water-rock interaction in fault zones can strongly affect nuclide migration. In this study, we analyzed the chemical composition of well-exposed fault rocks from the Atera Fault, Central Japan, to understand the variability and behavior of major and some selected trace elements. Hydrogen and oxygen isotope ratios in fault gouges, and carbon and oxygen isotope ratios in carbonates indicate that the two major clay-rich zones formed in bedrock at near surficial depth, consistent with observed deformation structures. Based on the analyses of chemical compositions, we identified depletion of SiO, NaO, KO, and light rare earth elements associated with the formation of smectite and kaolinite, and increase of CaO, MnO, and heavy rare earth elements associated with carbonate precipitation caused by the mixing of allochthonous basalt fragments during fault activities.
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：12 Percentile：64.04(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.
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%.
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.
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.
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.
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 extraction-recovery by solvent extraction methodKimura, Akihiro; Nishikata, Kaori; Tanase, Masakazu*; Fujisaki, Saburo*; Izumo, Hironobu; Tsuchiya, Kunihiko; Shiina, Takayuki*; Ota, Akio*; Takeuchi, Nobuhiro*; Ishihara, Masahiro
JAEA-Conf 2011-003, p.147 - 150, 2012/03
JP, 2011-173260Patent publication (In Japanese)
Tc is used as a radiopharmaceutical in the medical field for the diagnosis, and manufactured from Mo, the parent nuclide. In this study, the solvent extraction with MEK was selected, and preliminary experiments were carried out using Re instead of Tc. Two tests were carried out in the experiments; the one is the Re extraction test with MEK from Re-Mo solution, the other is the Re recovery test from the Re-MEK. As to the Re extraction test, and it was clear that the Re extraction yield was more than 90%. Two kinds of Re recovery tests, which are an evaporation method using the evaporator and an adsorption/elution method using the alumina column, were carried out. As to the evaporation method, the Re concentration in the collected solution increased more than 150 times. As to the adsorption/elution method, the Re concentration increased in the eluted solution more than 20 times.
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-MDP using Tc separated from Mo produced by 
Mo(
,2)MoNagai, Yasuki; Hatsukawa, Yuichi; Kin, Tadahiro; Hashimoto, Kazuyuki; Motoishi, Shoji; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Sato, Yuichi*; Kawauchi, Yukimasa*; et al.
Journal of the Physical Society of Japan, 80(8), p.083201_1 - 083201_4, 2011/08
Times Cited Count：15 Percentile：63.51(Physics, Multidisciplinary)We have for the first time succeeded to separate Tc from a Mo oxide sample irradiated by accelerator neutrons, and to formulate Tc-methylene diphosphonate (Tc-MDP). Mo, the mother nuclide of Tc, was produced by the Mo(,2)Mo reaction using about 14 MeV neutrons provided at the Fusion Neutronics Source of Japan Atomic Energy Agency. The Tc was separated from Mo by the sublimation method, and its radionuclide purity was confirmed to be higher than 99.99%. The labeling efficiency of Tc-MDP was shown to be higher than 99%. These values exceed the United States Pharmacopeia requirements for a fission product, Mo. Consequently, a Tc radiopharmaceutical preparation formed by using the mentioned Mo can be a promising substitute for the fission product Mo. A longstanding problem to ensure a reliable and constant supply of Mo in Japan can be partially mitigated.
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.
Mo production plan from Mo by (n,) reaction in JMTRIzumo, Hironobu; Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Tanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*
Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.77 - 82, 2011/02
no abstracts in English
Tc extraction techniques from Mo by (n,) reactionKimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Yuichi*
JAEA-Review 2010-053, 23 Pages, 2010/11
JAEA-Review-2010-053.pdf:2.52MB
Production techniques of Mo, parent nuclide of Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,) method is proposed in JMTR because of low-amount radioactive wastes and easy Tc production process. In this study, the production of the high-density MoO pellet and concentration techniques of Tc solution were developed. As the trial test, the MoO pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the Tc concentrating device with more than 80% concentration efficiency, was performed successfully.
Niwa, Masakazu; Mizuochi, Yukihiro*; Tanase, Atsushi*
Island Arc, 18(4), p.577 - 598, 2009/12
Times Cited Count：13 Percentile：8.95(Geosciences, Multidisciplinary)Architecture of fault/crush zones and their development histories are closely linked to the long-term stability of the underground environment. Herein, we studied part of the Atera Fault System, one of several large, active faults in Central Japan, and described the detailed mesoscopic and microscopic features of a crush zone to reveal its development at higher structural levels of the fault (i.e. several hundred meters to kilometers in depth). The zone is characterized by brittle fracturing and rock mass pulverization, lacks both ultracataclasite bands and any deformation structures showing pressure solution. The characteristics of the deformation structures suggest that the exposed crush zone was formed at a depth of less than several kilometers. Features of clay mineral and carbonate precipitations in the zone indicate the repetition of intense fragmentation and shear localization through periodic activities on the Atera Fault after the Pleistocene.
