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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

https://doi.org/10.1007/s10967-015-3975-y
 Times Cited Count：9 Percentile：60.64(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.

Journal Articles

Operation of the electron accelerators and $$gamma$$-ray irradiation facilities

Kaneko, Hirohisa; Hanaya, Hiroaki; Haneda, Noriyuki; Yamagata, Ryohei; Seito, Hajime; Kanazawa, Takao; Kojima, Takuji; Koyama, Shigeru*; Yamaguchi, Toshiyuki*; Kawashima, Ikuo*; et al.

JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 209, 2008/03

https://jopss.jaea.go.jp/pdfdata/JAEA-Review-2007-060.pdf

The accelerator served mainly for graft-polymerization for new material development, radiation effect study on semiconductors, and various experiments of outside users. The annual operation time for the electron accelerator is 597.4h(517h for vertical beams, 80.4h for horizontal beams) The Co-60 $$gamma$$-ray irradiation facilities consist of three buildings (8 rooms) and cover a wide dose-rate range from 0.04Gy/h to 20kGy/h with eight irradiation cells. The annual operation time for the cobalt first, second irradiation facilities and food irradiation facility is 20,844 h, 6,335 h and 3,150 h.

Journal Articles

Utilization of the electron accelerator and $$gamma$$-ray irradiation facilities

Kojima, Takuji; Kaneko, Hirohisa; Haneda, Noriyuki; Hanaya, Hiroaki; Yamagata, Ryohei; Seito, Hajime; Kanazawa, Takao; Koyama, Shigeru*; Yamaguchi, Toshiyuki*; Kawashima, Ikuo*; et al.

JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 208, 2008/03

https://jopss.jaea.go.jp/pdfdata/JAEA-Review-2007-060.pdf

An electron accelerator and three $$gamma$$ ray irradiation facilities were operated for various research subjects as operation plan in FY 2006 without serious trouble. The number of research subjects for the No.1 accelerator, the Cobalt No.1 facility, the Cobalt No.2 facility, and the Food irradiation facility, is 544, 159, 622, and 357, respectively.

Journal Articles

Utilization of the electron accelerator and $$gamma$$-ray irradiation facilities

Kanazawa, Takao; Kaneko, Hirohisa; Haneda, Noriyuki; Hanaya, Hiroaki; Yamagata, Ryohei; Seito, Hajime; Koyama, Shigeru*; Yamaguchi, Toshiyuki*; Kawashima, Ikuo*; Yagi, Norihiko*; et al.

JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 200, 2007/02

https://jopss.jaea.go.jp/pdfdata/JAEA-Review-2006-042.pdf

An electron accelerator and three $$gamma$$ ray irradiation facilities were operated without any trouble for various experiments in FY 2005. The operation of No.2 accelerator was terminated at April 2005. The number of experimental subjects was 544 for the No.1 accelerator, 287 for the Cobalt No.1 facility, 630 for the Cobalt No.2 facility, and 339 for the Food irradiation facility.

Journal Articles

Operation of the Co-60 $$gamma$$-ray irradiation facilities

Haneda, Noriyuki; Yamagata, Ryohei; Kaneko, Hirohisa; Hanaya, Hiroaki; Seito, Hajime; Kanazawa, Takao; Koyama, Shigeru*; Kawashima, Ikuo*; Yagi, Norihiko*; Takagi, Masahide*; et al.

JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 202, 2007/02

https://jopss.jaea.go.jp/pdfdata/JAEA-Review-2006-042.pdf

The Co-60 $$gamma$$-ray irradiation facilities consist of three buildings and cover a wide dose-rate range from 0.04Gy/h to 20kGy/h with eight irradiation cells. All the facilities have been operated without serious trouble and served for the following various R&D's of JAEA and out side users such as development of new materials, radiation resistance test, radiation biotechnology.

Oral presentation

Application of in-air micro-PIXE to biological sample

Sakurai, Eiko*; Yanai, Kazuhiko*; Ishii, Keizo*; Oyama, Ryohei*; Sakamaki, Manabu*; Yamanaka, Kentaro*; Yamazaki, Hiromichi*; Matsuyama, Shigeo*; Kamiya, Tomihiro; Sato, Takahiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Nuclear and radiochemical study of production and utilization of radioactive astatine isotopes using lithium ion beams at the tandem accelerator of JAEA-Tokai

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Amano, Ryohei*; Yamada, Norihiro*; Ishiguro, Rika*; Makii, Hiroyuki; Hashimoto, Kazuyuki

no journal, , 

An $$alpha$$ radioactive nuclide $$^{211}$$At is a prospective candidate for utilization in targeted alpha radiotherapy. We have started nuclear and radiochemical study of production and utilization of radioactive astatine isotopes using lithium ion beams at the tandem accelerator of JAEA-Tokai. We determined the excitation functions of astatine isotopes in the reaction of 29-48 MeV $$^7$$Li+$$^{nat}$$Pb and studied a chemical behavior of carrier-free radioactive astatine isotopes with a dry-chemistry method. Details will be shown in the presentation.

Oral presentation

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

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Amano, Ryohei*; Ri, Keiko*; Yamada, Norihiro*; Ishiguro, Rika*; Maeda, Eita*; Makii, Hiroyuki; Hashimoto, Kazuyuki; et al.

no journal, , 

We have started to study production and utilization of an $$alpha$$ radioactive nuclide $$^{211}$$At which is a prospective candidate for targeted alpha radiotherapy. We determined production cross sections of astatine radioisotopes in the reaction of 29-48 MeV $$^7$$Li+$$^{nat}$$Pb by $$alpha$$-ray and $$gamma$$-ray spectrometry at the tandem accelerator of JAEA-Tokai. Besides, we developed a simple dry-chemical method for separation of astatine.

Oral presentation

Nuclear and radiochemical study of production and utilization of radioactive astatine isotopes in the Li + $$^{nat}$$Pb reaction

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Amano, Ryohei*; Maeda, Eita*; Yamada, Norihiro*; Makii, Hiroyuki; Watanabe, Shigeki; Ishioka, Noriko; Hashimoto, Kazuyuki

no journal, , 

Oral presentation

Nuclear and radiochemical study of production and utilization of radioactive astatine isotopes in the Li+$$^{nat}$$Pb reaction; Aim at the new cancer medical treatment by $$alpha$$-emitting radioisotopes

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

no journal, , 

no abstracts in English

Oral presentation

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

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

no journal, , 

Production cross sections of astatine in 29-57 MeV $$^7$$Li + $$^{rm nat}$$Pb 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 the $$^7$$Li + $$^{rm nat}$$Pb reaction. It indicates that the breakup of $$^7$$Li plays a rule in the $$^7$$Li + $$^{rm nat}$$Pb reaction. Besides, we have developed a dry-distillation method which separates carrier-free astatine from an irradiated lead target.

Oral presentation

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

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

no journal, , 

To promote utilization of a radioactive nuclide $$^{211}$$At which draws increasing attention as a promissing $$alpha$$-emitter for targeted alpha therapy, we have measured production cross sections of astatine isotopes in the 29-57 MeV$$^7$$Li+$$^{nat}$$Pb reaction using the tandem accelerator of JAEA-Tokai, providing nuclear data for production. For pharmaceutical study and so on, beside, we have developed a new separation procedure based on a dry-distillation method which separates carrier free astatine isotopes from lead targets with high radiochemical and chemical purity and high yields.

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 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.

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