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Journal Articles

Technical estimation for mass production of highly-concentrated $$^{rm 99m}$$Tc solution from $$^{99}$$Mo to be obtained by ($$n,gamma$$) reaction; A Preliminary study using inactive Re instead of $$^{rm 99m}$$Tc

Tanase, 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

https://doi.org/10.3769/radioisotopes.65.237

no abstracts in English

JAEA Reports

Establishment of experimental system for $$^{99}$$Mo/$$^{99m}$$Tc production by neutron activation method

Ishida, 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 $$^{99}$$Mo/$$^{99m}$$Tc by neutron activation method ((n, $$gamma$$) method) using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center. The specific radioactivity of $$^{99}$$Mo by (n, $$gamma$$) method is extremely low compared with that by fission method ((n,f) method), and as a result, the radioactive concentration of the obtained $$^{99m}$$Tc solution is also lowered. To solve the problem, we propose the solvent extraction with methyl ethyl ketone (MEK) for recovery of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n, $$gamma$$) method. We have developed the $$^{99}$$Mo/$$^{99m}$$Tc separation/extraction/concentration devices and have carried out the performance tests for recovery of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n, $$gamma$$) method. In this paper, in order to establish an experimental system for $$^{99}$$Mo/$$^{99m}$$Tc production, the R&D results of the system are summarized on the improvement of the devices for high-recovery rate of $$^{99m}$$Tc, on the dissolution of the pellets, which is the high-density molybdenum trioxide (MoO$$_{3}$$) pellets irradiated in Kyoto University Research Reactor (KUR), on the production of $$^{99m}$$Tc, and on the inspection of the recovered $$^{99m}$$Tc solutions.

Journal Articles

Changes in chemical composition caused by water-rock interactions across a strike-slip fault zone; Case study of the Atera Fault, Central Japan

Niwa, Masakazu; Mizuochi, Yukihiro*; Tanase, Atsushi*

Geofluids, 15(3), p.387 - 409, 2015/08

https://doi.org/10.1111/gfl.12096
 Times Cited Count：8 Percentile：44.02(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$$_{2}$$, Na$$_{2}$$O, K$$_{2}$$O, 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.

Journal Articles

Mechanism of $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution from zirconium-based material in $$^{99}$$Mo/$$^{rm 99m}$$Tc generator column using neutron-irradiated natural molybdenum

Awaludin, 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

https://doi.org/10.1007/s10967-014-3606-z
 Times Cited Count：8 Percentile：59.1(Chemistry, Analytical)

In this study, the $$^{99}$$Mo adsorption and $$^{rm 99m}$$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 $$^{rm 99m}$$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 $$^{rm 99m}$$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 $$^{rm 99m}$$Tc can be eluted from the material column in TcO$$_{4}$$$$^{-}$$ since oxidizing agent was needed in the elution process.

JAEA Reports

Fabrication technology development and characterization of irradiation targets for $$^{99}$$Mo/$$^{rm 99m}$$Tc production by (n,$$gamma$$) method

Nishikata, 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 $$^{99}$$Mo/$$^{99m}$$Tc by (n, $$gamma$$) method using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center of the Japan Atomic Energy Agency. $$^{99}$$Mo is usually produced by fission method. On the other hand, $$^{99}$$Mo/$$^{99m}$$Tc production by the (n, $$gamma$$) method has advantages for radioactive waste, cost reduction and non-proliferation. However, the specific radioactivity per unit volume by the (n, $$gamma$$) method is low compared with the fission method, and that is the weak point of the (n, $$gamma$$) method. This report summarizes the investigation of raw materials, the fabrication tests of high-density MoO$$_{3}$$ pellets by the plasma sintering method for increasing of $$^{98}$$Mo contents and the characterization of sintered high-density MoO$$_{3}$$ pellets.

Journal Articles

Development of $$^{99m}$$Tc production from (n,$$gamma$$)$$^{99}$$Mo based on solvent extraction

Kimura, 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)

$$^{99m}$$Tc is generated by decay of $$^{99}$$Mo. Production of $$^{99}$$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,$$gamma$$) method has lately attracted considerable attention. The (n,$$gamma$$) 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 $$^{99m}$$Tc with alumina column. In this paper, a practical production of $$^{99m}$$Tc was tried by the method with 1Ci of $$^{99}$$Mo produced in MPR-30. The recovery yields were approximately 70%. Impurity of $$^{99}$$Mo was less than 4.0$$times$$10$$^{-5}$$% and the radiochemical purity was over 99.2%.

Journal Articles

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

Tsuchiya, 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

http://www.invap.com.ar/ismtr/images/stories/trabajos/Tsuchiya-Paper.pdf
http://www.invap.com.ar/ismtr/images/stories/trabajos/Tsuchiya-Presentation.pdf

no abstracts in English

Journal Articles

Development of $$^{99m}$$Tc production from (n,$$gamma$$)$$^{99}$$Mo based on solvent extraction and column chromatography

Kimura, 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

http://www.invap.com.ar/ismtr/images/stories/trabajos/Ohta-Paper.pdf
http://www.invap.com.ar/ismtr/images/stories/trabajos/Ohta-Presentation.pdf
JP, 2011-173260   Patent publication (In Japanese)

This research is development of $$^{99m}$$Tc production. $$^{99m}$$Tc is generated by decay of $$^{99}$$Mo. The supply of $$^{99}$$Mo in Japan depends entirely on the import from foreign countries. Thus, it is needed to supply $$^{99}$$Mo stably by the domestic manufacturing. A practical production of $$^{99m}$$Tc was tried by the method with 1 Ci of $$^{99}$$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$$_{3}$$ was irradiated for 5 days in MPR-30. Impurity of $$^{99}$$Mo was less than 4.4$$times$$10$$^{-5}$$%, 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.

Journal Articles

Fabrication and characterization of high-density MoO$$_{3}$$ pellets

Nishikata, 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 $$^{99}$$Mo depends on imports from foreign countries. Japan Atomic Energy Agency (JAEA) has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm 99m}$$Tc, and JAEA has performed the R&D for $$^{99}$$Mo production by (n,$$gamma$$) method in JMTR. Generally, molybdenum oxide (MoO$$_{3}$$) is the most popular chemical form as irradiation target for the $$^{99}$$Mo production. However, the $$^{99}$$Mo production capacity is low because of low (n,$$gamma$$) cross section and isotope composition of $$^{98}$$Mo in Mo. Thus, it is necessary to fabricate the MoO$$_{3}$$ pellets with high density for the increase of the $$^{99}$$Mo production amount. In this study, MoO$$_{3}$$ pellets fabricated by a plasma activated sintering were developed and characterization of MoO$$_{3}$$ pellets was carried out.

Journal Articles

Development of $$^{rm 99m}$$Tc production from (n, $$gamma$$) $$^{99}$$Mo

Tanase, 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

http://www.murr.missouri.edu/ismtr/papercall/Papers/Chiyoda%20Technol/Tanase_M=PAPER_Dev%20of%20Tc99m%20Prod%20from%20n-g%20Mo99.pdf

$$^{rm 99m}$$Tc is used as a radiopharmaceutical and manufactured from the parent nuclide of $$^{99}$$Mo. Extraction method of $$^{rm 99m}$$Tc from (n, $$gamma$$) $$^{99}$$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 $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities. The method proposed would be applicable to a practical production of $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities.

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

http://www.murr.missouri.edu/ismtr/papercall/Papers/JAEA/Tsuchiya_K=PAPER_Dev%20of%20Mo99-Tc99m%20Domestic%20Prod%20with%20HighDens%20MoO3%20Pellets.pdf

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.

Journal Articles

Fabrication development of high-density MoO$$_{3}$$ pellets for (n, $$gamma$$) $$^{99}$$Mo production

Nishikata, 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

http://www.murr.missouri.edu/ismtr/papercall/Papers/Ecodesign/Suzuki_K_PAPER=Fabrication%20Dev%20of%20High%20Dens%20MoO3%20Pellets.pdf

In this study, experimental fabrication tests of the high-density MoO$$_{3}$$ 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$$_{3}$$ Pellets for the future domestic production of $$^{rm 99m}$$Tc. The irradiation tests and characterization with these pellets will be carried out under the international cooperation.

Journal Articles

Development of high density MoO$$_{3}$$ pellets for production of $$^{99}$$Mo medical isotope

Kimura, Akihiro; Sato, Yuichi*; Tanase, Masakazu*; Tsuchiya, Kunihiko

IOP Conference Series; Materials Science and Engineering, 18(4), p.042001_1 - 042001_4, 2011/10

https://doi.org/10.1088/1757-899X/18/4/042001

In the medical field, the radioisotopes are indispensable. Especially, $$^{99m}$$Tc is most commonly used as a radiopharmaceutical. However, the supply of $$^{99}$$Mo in Japan depends fully on the import from foreign countries. JMTR has a plan to produce a medical isotope of $$^{99}$$Mo, the parent nuclide of $$^{99m}$$Tc by the (n,$$gamma$$) 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$$_{3}$$) pellets. However, MoO$$_{3}$$ is low sublime temperature and it is difficult to produce the pellets with high density. In this study, MoO$$_{3}$$ pellets were produced by two kinds of production methods. As a result, MoO$$_{3}$$ pellet of about 70% TD was obtained by CIP and MoO$$_{3}$$ pellet of over 95% TD was obtained by SPS.

Journal Articles

Successful labeling of $$^{rm 99m}$$Tc-MDP using $$^{rm 99m}$$Tc separated from $$^{99}$$Mo produced by $$^{100}$$Mo($textit{n}$,2$textit{n}$)$$^{99}$$Mo

Nagai, 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

https://doi.org/10.1143/JPSJ.80.083201
 Times Cited Count：14 Percentile：64.53(Physics, Multidisciplinary)

We have for the first time succeeded to separate $$^{rm 99m}$$Tc from a Mo oxide sample irradiated by accelerator neutrons, and to formulate $$^{rm 99m}$$Tc-methylene diphosphonate ($$^{rm 99m}$$Tc-MDP). $$^{99}$$Mo, the mother nuclide of $$^{rm 99m}$$Tc, was produced by the $$^{100}$$Mo($textit{n}$,2$textit{n}$)$$^{99}$$Mo reaction using about 14 MeV neutrons provided at the Fusion Neutronics Source of Japan Atomic Energy Agency. The $$^{rm 99m}$$Tc was separated from $$^{99}$$Mo by the sublimation method, and its radionuclide purity was confirmed to be higher than 99.99%. The labeling efficiency of $$^{rm 99m}$$Tc-MDP was shown to be higher than 99%. These values exceed the United States Pharmacopeia requirements for a fission product, $$^{99}$$Mo. Consequently, a $$^{rm 99m}$$Tc radiopharmaceutical preparation formed by using the mentioned $$^{99}$$Mo can be a promising substitute for the fission product $$^{99}$$Mo. A longstanding problem to ensure a reliable and constant supply of $$^{99}$$Mo in Japan can be partially mitigated.

JAEA Reports

Feasibility study of sublimation type $$^{99m}$$Tc master-milker; Comparison with PZC based wet method

Ishitsuka, 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 $$^{99m}$$Tc master-milker was carried out as a $$^{99}$$Mo/$$^{99m}$$T production development with the JMTR. As the feasibility study, the experimental equipment for sublimation method and wet method with PZC based $$^{99m}$$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 $$^{99m}$$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$$_{3}$$ comparing with the wet method. On the other hand, disadvantageous point is that the $$^{99m}$$Tc recovery rate decreases with the increase of treating amount of MoO$$_{3}$$.

Journal Articles

$$^{99}$$Mo production plan from $$^{98}$$Mo by (n,$$gamma$$) reaction in JMTR

Izumo, 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

JAEA Reports

Development of $$^{rm 99m}$$Tc extraction techniques from $$^{99}$$Mo by (n,$$gamma$$) reaction

Kimura, 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 $$^{99}$$Mo, parent nuclide of $$^{rm 99m}$$Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,$$gamma$$) method is proposed in JMTR because of low-amount radioactive wastes and easy $$^{rm 99m}$$Tc production process. In this study, the production of the high-density MoO$$_{3}$$ pellet and concentration techniques of $$^{rm 99m}$$Tc solution were developed. As the trial test, the MoO$$_{3}$$ pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate $$^{rm 99m}$$Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the $$^{rm 99m}$$Tc concentrating device with more than 80% concentration efficiency, was performed successfully.

Journal Articles

Reconstructing the evolution of fault zone architecture; Field-based study of the core region of the Atera Fault, Central Japan

Niwa, Masakazu; Mizuochi, Yukihiro*; Tanase, Atsushi*

Island Arc, 18(4), p.577 - 598, 2009/12

https://doi.org/10.1111/j.1440-1738.2009.00674.x
 Times Cited Count：12 Percentile：9.83(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.

Journal Articles

Development of electrochemical hydrogen pump under vacuum condition for a compact tritium gas cycling system

Kato, Mineo; Ito, Takeshi*; Sugai, Hiroyuki; Kawamura, Yoshinori; Hayashi, Takumi; Nishi, Masataka; Tanase, Masakazu; Matsuzaki, Teiichiro*; Ishida, Katsuhiko*; Nagamine, Kanetada*

Fusion Science and Technology, 41(3), p.859 - 862, 2002/05

JAERI has a plane to develop a compact tritium gas recycling system for fusion research. This system is also very attractive for the muon-catalyzed fusion ($$mu$$CF) research at RIKEN-RAL Muon Facility in UK. For the research, JAERI has produced high purity tritium gas of 1,500 Ci and transported it to the Facility. In the $$mu$$CF experiments, the tritium gas was diluted by the deuterium in an optional concentration and the used tritium gas was carried back by the tritium transport container developed to JAERI. If it is possible to recycle the diluted tritium gas, i.e., the used tritium gas is enriched in the experimental site, the $$mu$$CF experiments should be conducted efficiently. rom the above point of view, in this paper, we propose the compact tritium gas recycling system based on the gas chromatography that has already developed in JAERI and a proton conductor.

Journal Articles

To meet with a book, "Asimov's Chronology of Science and Discovery" by Isaac Asimov

Tanase, Masakazu

Hoshasen To Sangyo, (90), p.59 - 62, 2001/06

http://ci.nii.ac.jp/naid/40004433207

no abstracts in English

64 (Records 1-20 displayed on this page)