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Journal Articles

Corrosion behavior of iron-chrome alloys in liquid bismuth

Takai, Toshihide; Furukawa, Tomohiro; Watanabe, Shigeki*; Ishioka, Noriko*

Mechanical Engineering Journal (Internet), 9(4), p.21-00397_1 - 21-00397_11, 2022/08

For the mass production of astatine-211, a promising radiopharmaceutical for cancer treatment, the National Institute for Quantum and Radiological Science and Technology has proposed the innovative "Liquid Bismuth Target System." The target window in this system must be made from a material that resists the highly corrosive liquid bismuth environment. To meet this requirement, a promising target window material was selected in corrosion experiments performed in stagnant liquid bismuth. Based on knowledge of corrosion in liquid lead-bismuth eutectic gained during the development of fast reactors and accelerator-driven subcritical systems, experiments were carried out under saturated dissolved oxygen and low oxygen conditions, and the corrosion behaviors of the specimens were evaluated. The FeCrAl-alloy exhibited the most excellent corrosion resistance, followed by FeCrMo-alloy. Both materials are suitable candidates for the target window.

Journal Articles

Production and separation of astatine isotopes in the $$^7$$Li + $$^{nat}$$Pb reaction

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Maeda, Eita*; Watanabe, Shigeki; Hashimoto, Kazuyuki; Ishioka, Noriko; Makii, Hiroyuki; Toyoshima, Atsushi; Yamada, Norihiro*; et al.

Journal of Radioanalytical and Nuclear Chemistry, 304(3), p.1077 - 1083, 2015/06

 Times Cited Count:9 Percentile:60.27(Chemistry, Analytical)

Production cross sections of astatine isotopes $$^{207-211}$$At in the 29-57 MeV $$^7$$Li induced reaction with $$^{nat}$$Pb target have been measured by $$alpha$$- and $$gamma$$-ray spectrometry. Excitation functions of production cross sections have been compared with a statistical model calculation to study the reaction mechanism of $$^7$$Li + $$^{nat}$$Pb. Considerably small experimental cross sections of $$^{210}$$At and $$^{209}$$At compared with the calculation were clearly observed at incident energies higher than 44 MeV, indicating that the effects of breakup reaction play a role. A chemical separation of astatine from an irradiated lead target has been studied with a dry-distillation method. A complementary way to produce astatine isotopes has been developed.

JAEA Reports

Annual limits on intake and concentration limits for radioactive isotopes of astatine

Togawa, Orihiko

JAERI-M 93-022, 35 Pages, 1993/02

JAERI-M-93-022.pdf:0.89MB

no abstracts in English

Oral presentation

Production and utilization of astatine radioisotopes using $$^{7}$$Li ion beams

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Amano, Ryohei*; Maeda, Eita*; Taniguchi, Takumi*; Murakami, Kento*; Watanabe, Shigeki; Suzuki, Hiroyuki; Ishioka, Noriko; et al.

no journal, , 

In general, an $$alpha$$-emitter $$^{211}$$At which is a prospective candidate for utilization in targeted alpha radiotherapy is produced through the $$^{209}$$Bi($$^{4}$$He, 2n)$$^{211}$$At reaction. In contrast, our project is focusing on the production in the $$^{209}$$Bi($$^{7}$$Li, 5n)$$^{211}$$Rn reaction. This enables us to supply $$^{211}$$At in a $$^{211}$$Rn/$$^{211}$$At generator system. The daughter $$^{211}$$At (7.2 h half-life) is extracted from the parent $$^{211}$$Rn (14h), expanding time-frame for transportation and use of $$^{211}$$At. To use astatine and iodine radioisotopes in our project, the excitation functions of $$^{209}$$Bi($$^{7}$$Li, xn)$$^{216-x}$$Rn, $$^{nat}$$Pb($$^{7}$$Li, xn)$$^{nat-x}$$At and $$^{nat}$$Sn($$^{7}$$Li, xn)$$^{nat-x}$$I reactions have been measured. In addition to that, separation techniques have been developed. We report not only on the production and separation of astatine and iodine radioisotopes in the reactions but also on the utilization of those radioisotopes.

Oral presentation

Development of $$^{211}$$Rn/$$^{211}$$At generator for targeted alpha therapy

Washiyama, Koshin*; Maeda, Eita*; Yokoyama, Akihiko*; Nishinaka, Ichiro; Taniguchi, Takumi*; Yamada, Norihiro*; Makii, Hiroyuki; Toyoshima, Atsushi; Amano, Ryohei*

no journal, , 

A $$^{211}$$Rn/$$^{211}$$At generator for targeted alpha therapy has been developed.

Oral presentation

Production of $$^{211}$$At for alpha radiotherapy via $$^{209}$$Bi($$^7$$Li,5n)$$^{211}$$Rn

Nishinaka, Ichiro; Washiyama, Koshin*; Yokoyama, Akihiko*; Maeda, Eita*; Hashimoto, Kazuyuki; Makii, Hiroyuki

no journal, , 

A $$^{211}$$Rn/$$^{211}$$At generator has been proposed to supply a radiotracer $$^{211}$$At with a half-life (T$$_{1/2}$$ = 7.2 h) for medical applications. To establish a technology of the $$^{211}$$Rn/$$^{211}$$At generator, $$^{211}$$Rn (T$$_{1/2}$$ = 14.7 h) has to be produced through the $$^{209}$$Bi($$^7$$Li, 5n)$$^{211}$$Rn reaction without melting bismuth metal targets due to heat produced by the irradiation of 60 MeV $$^7$$Li ion beams. In this work, we have studied the effects of a He gas cooling system of an irradiation chamber constructed for the production of $$^{211}$$Rn. Irradiations were carried out at the JAEA tandem accelerator using the irradiation chamber equipped with the He gas cooling system. The results show that the He gas effectively cools the targets and the cooling efficiency is nearly independent of the pressure ($$>$$ 1 kPa) and the flow rate ($$sim$$20 L/min) of the He gas.

Oral presentation

Production of alpha-emitting radioisotopes using the cyclotron facilities at Osaka University and JAEA Takasaki, and the Tandem accelerator at Tokai, JAEA

Washiyama, Koshin*; Amano, Ryohei*; Maeda, Eita*; Yokoyama, Akihiko*; Nishinaka, Ichiro; Takahashi, Naruto*; Shinohara, Atsushi*; Watanabe, Shigeki; Ishioka, Noriko

no journal, , 

In order to use of an alpha emitter for targeted alpha therapy, we have started the production and the utilization of $$^{211}$$At using 30 MeV $$^4$$He particle in the $$^{209}$$Bi($$^4$$He, 2n)$$^{211}$$At nuclear reaction at cyclotron facilities of Osaka University and JAEA Takasaki. In addition to that, we have been developing a $$^{211}$$Rn/$$^{211}$$At generator to expand the availability of $$^{211}$$At to wide range of populations far away from cyclotron facilities. The results of studies on the At-chemistry for clinical use and on the development of the $$^{211}$$Rn/$$^{211}$$At generator will be presented. And a review of current status of targeted alpha therapy in Japan will be also introduced.

Oral presentation

Development of $$^{211}$$Rn/$$^{211}$$At generator at the JAEA tandem accelerator

Nishinaka, Ichiro

no journal, , 

Research and development of a $$^{211}$$Rn/$$^{211}$$At generator has been conducted at the JAEA tandem accelerator. The outline and the current state of the research and development program are presented.

Oral presentation

Redox and solvent extraction behavior of astatine

Toyoshima, Atsushi; Kanda, Akimitsu*; Ikeda, Takumi*; Yoshimura, Takashi*; Shinohara, Atsushi*; Yano, Shinya*; Komori, Yukiko*; Haba, Hiromitsu*

no journal, , 

Astatine (At) is reported to be bound in a few oxidation states in aqueous solutions. However, their valencies and chemical species are experimentally not identified. In this study, we studied redox behavior of At using redox agents and using a flow electrolytic column. $$^{211}$$At was produced in the $$^{209}$$Bi($$alpha$$, 2${it n}$)$$^{211}$$At reaction and was then separated from the target by a distillation method. Then, redox of At was carried out in 1.0 M HClO$${_4}$$ using redox agents or by an electrolysis. After the redox, solvent extraction with HDEHP was performed to identify the redox reactions. Using the redox agents, extraction yields of At were different between the conditions with oxidizing or reducing agents and without redox agents. This means that redox reactions of At can be identified under the present extraction conditions. On the other hand, by the electrolysis, extraction yields of At were almost constant against the variation of applied potential. This is possibly due to the restoration to the original oxidation state after the electrolysis. In the future, we will perform flow electrolytic column chromatography available for simultaneous electrolysis and separation.

Oral presentation

Development of cavity ring-down spectroscopy apparatus for chemical identification of carrier-free radioiodine and astatine in gas phase

Toyoshima, Atsushi; Aoyagi, Noboru

no journal, , 

Although carrier-free radiotracers are utilized in lots of research fields, their chemical forms have not been identified by UV/vis. spectroscopy because of their micro quantities. In this study, we are developing an apparatus for cavity ring-down spectroscopy to perform absorption spectroscopy of radioiodine and astatine in a gas-phase. With this apparatus, ultra-sensitive absorption measurement is realized by making injected pulse-laser go back and forth tens of thousand times between facing mirrors. Intensity of laser in the cavity becomes weaker by its escaping through the mirrors and by absorption by samples. Absorption coefficients are obtained from difference in the life-time of escaped light between blank and sample measurements. Chemical species are expected to be characterized by measuring absorption coefficients at various wavelength and comparing these with known spectra and theoretical calculations. In the symposium, present status of the development will be reported.

Oral presentation

Corrosion behavior of iron-chrome alloys in liquid bismuth

Takai, Toshihide; Furukawa, Tomohiro; Watanabe, Shigeki*; Ishioka, Noriko*

no journal, , 

For the mass production of astatine-211, a promising radiopharmaceutical for cancer treatment, the National Institute for Quantum and Radiological Science and Technology has proposed the innovative "Liquid Bismuth Target System." The target window in this system must be made from a material that resists the highly corrosive liquid bismuth environment. To meet this requirement, a promising target window material was selected in corrosion experiments performed in stagnant liquid bismuth. Based on knowledge of corrosion in liquid lead-bismuth eutectic gained during the development of fast reactors and accelerator-driven subcritical systems, experiments were carried out under saturated dissolved oxygen and low oxygen conditions, and the corrosion behaviors of the specimens were evaluated. The FeCrAl-alloy exhibited the most excellent corrosion resistance, followed by FeCrMo-alloy. Both materials are suitable candidates for the target window.

11 (Records 1-11 displayed on this page)
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