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Journal Articles

Development of the treatment method for difficult wastes aimed at decommissioning of JMTR; Structural materials of reactor and used ion-exchange resins

Seki, Misaki; Nakano, Hiroko; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Takeuchi, Tomoaki; Ide, Hiroshi; Tsuchiya, Kunihiko

Dekomisshoningu Giho, (62), p.9 - 19, 2020/09

Japan Materials Testing Reactor (JMTR) has been contributing to various research and development activities such as the fundamental research of nuclear materials/fuels, safety research and development of power reactors, and radioisotope production since the beginning of the operation in 1968. JMTR, however, was decided as a one of decommission facilities in April 2017 and it is taken an inspection of a plan concerning decommissioning because the performance of JMTR does not confirm with the stipulated earthquake resistance. As aluminum and beryllium are used for the core structural materials in JMTR, it is necessary to establish treatment methods of these materials for the fabrication of stable wastes. In addition, a treatment method for the accumulated spent ion-exchange resins needs to be examined. This report describes the overview of these examination situations.

Journal Articles

Research on activation assessment of a reactor structural materials for decommissioning, 2

Seki, Misaki; Ishikawa, Koji*; Sano, Tadafumi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2019, P. 279, 2020/08

no abstracts in English

Journal Articles

Radiochemical research for the advancement of $$^{99}$$Mo/$$^{rm 99m}$$Tc generator by (n,$$gamma$$) method, 2

Fujita, Yoshitaka; Seki, Misaki; Namekawa, Yoji*; Nishikata, Kaori; Kato, Yoshiaki; Sayato, Natsuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; Hori, Junichi*; et al.

KURNS Progress Report 2019, P. 157, 2020/08

no abstracts in English

Journal Articles

Research on activation assessment of a reactor structural materials for decommissioning

Seki, Misaki; Ishikawa, Koji*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2018, P. 257, 2019/08

no abstracts in English

Journal Articles

Radiochemical research for the advancement of $$^{99}$$Mo/$$^{rm 99m}$$Tc generator by (n,$$gamma$$) method

Fujita, Yoshitaka; Seki, Misaki; Namekawa, Yoji*; Nishikata, Kaori; Kimura, Akihiro; Shibata, Akira; Sayato, Natsuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2018, P. 155, 2019/08

no abstracts in English

Journal Articles

Status of JMTR decommissioning plan formulation, 2

Otsuka, Kaoru; Ide, Hiroshi; Nagata, Hiroshi; Omori, Takazumi; Seki, Misaki; Hanakawa, Hiroki; Nemoto, Hiroyoshi; Watanabe, Masao; Iimura, Koichi; Tsuchiya, Kunihiko; et al.

UTNL-R-0499, p.12_1 - 12_8, 2019/03

no abstracts in English

Oral presentation

Two step pressurization in pulsed electric current sintering of MoO$$_{3}$$ for production of radioactive isotopes

Suematsu, Hisayuki*; Seki, Misaki*; Sato, Soma*; Nanko, Makoto*; Tsuchiya, Kunihiko; Nishikata, Kaori; Suzuki, Tsuneo*; Nakayama, Tadachika*; Niihara, Koichi*

no journal, , 

no abstracts in English

Oral presentation

Pulsed Electric Current Sintering of MoO3 for Production of Radioactive Isotopes

Suematsu, Hisayuki*; Sato, Soma*; Seki, Misaki*; Nanko, Makoto*; Nishikata, Kaori; Suzuki, Yoshitaka; Tsuchiya, Kunihiko; Suzuki, Tsuneo*; Nakayama, Tadachika*; Niihara, Koichi*

no journal, , 

$$^{99m}$$Tc has been utilized as a radioactive isotope in medical applications. The majority of this isotope has been separated from nuclear fission products in testing reactors with highly enriched $$^{235}$$U fuel. However, these reactors have been shut down because of the age and the nuclear security reasons. On the other hand, a nuclear reaction method has been proposed. This method is to irradiate $$^{98}$$Mo by neutrons in a reactor to form $$^{98}$$Mo and then to decay to $$^{99m}$$Tc. As the target, MoO$$_{3}$$ pellets are required. However, because of the low evaporation temperature (700 $$^{circ}$$C) and coarse grain size of $$^{98}$$Mo enriched powder, it was difficult to obtain high density MoO$$_{3}$$ pellets. To overcome this problem, a two-step loading method in pulsed electric current sintering was carried out in this study.

Oral presentation

Nuclide separation by water for development of $$^{99}$$Mo/$$^{99m}$$Tc generator for medical

Seki, Misaki*; Suematsu, Hisayuki*; Nakayama, Tadachika*; Suzuki, Tsuneo*; Niihara, Koichi*; Suzuki, Tatsuya*; Tsuchiya, Kunihiko; Duong Van, D.*

no journal, , 

no abstracts in English

Oral presentation

Pulsed electric current sintering of MoO$$_{3}$$ and the neutron irradiation tests

Suematsu, Hisayuki*; Seki, Misaki; Nakayama, Tadachika*; Nishikata, Kaori; Nanko, Makoto*; Suzuki, Tatsuya*; Tsuchiya, Kunihiko

no journal, , 

Pulsed electric current sintering (PECS) of MoO$$_{3}$$ was carried out for a high density target to produce $$^{99m}$$Tc from $$^{98}$$Mo in a nuclear reactor. The green compacts of MoO$$_{3}$$ were heated in a PECS apparatus with a heating rate of 100 $$^{circ}$$C/min to 450 - 550 $$^{circ}$$C in vacuum and changing the pressurization profile from 0 to 40 MPa. After two step pressurization for sintering at 550 $$^{circ}$$C, the sintered MoO$$_{3}$$ bulk had a relative density of 94%, which was higher than that of one step pressurization. Direct temperature measurements near the sample were carried out. The results indicated that the sample temperature was higher for the two step than for the one step pressurization even in the same die temperature experiments. By the low pressure in two step pressurization, it was thought that open pores remained in the sintered body to reduce MoO$$_{3}$$ in vacuum. This oxygen depleted MoO$$_{3-x}$$ grains showed low electrical resistivity and formed a current path in the sintered body to increase the temperature to increase the relative density.

Oral presentation

Mo adsorption and $$^{99m}$$Tc elution properties of alumina using (n, $$gamma$$)$$^{99}$$Mo

Fujita, Yoshitaka; Seki, Misaki; Sano, Tadafumi*; Suzuki, Tatsuya*; Kitagawa, Tomoya*; Nishikata, Kaori; Matsukura, Minoru*; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Examination of stabilization treatment method of radioactive aluminum waste

Seki, Misaki; Ishikawa, Koji*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Suzuki, Yumi*; Tanaka, Atsushi*; Kawakami, Tomohiko*; Ide, Hiroshi; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Examination of stabilization treatment method of radioactive aluminum waste, 2; Removal properties of impurities in the stabilization treatment process

Seki, Misaki; Ishikawa, Koji*; Fujihara, Yasuyuki*; Sano, Tadafumi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Ide, Hiroshi; Hori, Junichi*; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

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