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Journal Articles

Production of diagnostic $$^{99}$$Mo/$$^{99m}$$Tc by PWR

Nasu, Takuya*; Fujita, Yoshitaka

Enerugi Rebyu, 42(10), p.15 - 18, 2022/09

no abstracts in English

Journal Articles

Production of $$^{225}$$Ac for Targeted Alpha Therapy (TAT) using the experimental fast reactor Joyo

Maeda, Shigetaka; Kitatsuji, Yoshihiro

Enerugi Rebyu, 42(10), p.19 - 22, 2022/09

Ac-225 is attracting attention as an alpha-emitting medical radioisotope. Since its demand is expected to increase, domestic production of Ac-225 is required from the viewpoint of Japan's medical research and economic security. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity that can be produced in the experimental fast reactor Joyo and designed the concept that upgrades the existing facilities for transporting the irradiated target from Joyo to a neighboring PIE facility rapidly. Efficient Actinium-225 Separation from Ra-226 irradiated in a fast reactor was studied. Ba and La were used as alternatives to Ra and Ac, respectively. By using DGA resin as an adsorbent, it can be expected that Ra and impurities generated by irradiation will be removed and Ac will be isolated. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.

JAEA Reports

Annual report of Department of Research Reactor and Tandem Accelerator, JFY2015; Operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2017-027, 142 Pages, 2018/01

JAEA-Review-2017-027.pdf:5.75MB

The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3 (Japan Research Reactor No.3), JRR-4 (Japan Research Reactor No.4), NSRR (Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2015.

Journal Articles

Deuteron nuclear data for the design of accelerator-based neutron sources; Measurement, model analysis, evaluation, and application

Watanabe, Yukinobu*; Kin, Tadahiro*; Araki, Shohei*; Nakayama, Shinsuke; Iwamoto, Osamu

EPJ Web of Conferences, 146, p.03006_1 - 03006_6, 2017/09

 Times Cited Count:2 Percentile:78.04(Nuclear Science & Technology)

The design of $$(d,xn)$$ neutron sources requires comprehensive nuclear data of deuteron-induced reactions. Therefore, we have launched a research project on deuteron nuclear data, which is composed of measurements, theoretical model code development, cross section evaluation, and application to production of radioisotopes for medical use. Our goal is to develop a state-of-art deuteron nuclear data library up to 200 MeV necessary for the design of accelerator neutron sources with deuteron beam. The present status is reported in the presentation.

Journal Articles

Separation, purification of $$^{177}$$Lu$$^{m}$$ and preparation of $$^{177}$$Lu$$^{m}$$-EDTMP

Chen, D.*; Hashimoto, Kazuyuki

Journal of Nuclear and Radiochemistry, 26(2), p.84 - 87, 2004/05

no abstracts in English

Journal Articles

Production of no-carrier-added $$^{177}$$Lu via the $$^{176}$$Yb(n,$$gamma$$)$$^{177}$$Yb$$rightarrow$$$$^{177}$$Lu process

Hashimoto, Kazuyuki; Matsuoka, Hiromitsu; Uchida, Shoji*

Journal of Radioanalytical and Nuclear Chemistry, 255(3), p.575 - 579, 2003/03

 Times Cited Count:42 Percentile:91.79(Chemistry, Analytical)

The $$beta^{-}$$ emitter $$^{177}$$Lu is a promising therapeutic radioisotope for the treatment of cancer. It has a half-life of 6.73 days and maximum $$beta^{-}$$ energy of 498 keV, resulting in a short range of radiation in tissue. The decay is accompanied by the emission of low energy $$gamma$$-radiation with $$E_{gamma}$$ = 208 keV (11.0%) and 113 keV (6.4%) suitable for simultaneous imaging. Lutetium-177 can be usually produced at nuclear reactors with high yield and high specific radioactivity by the $$^{176}$$Lu(n,$$gamma$$)$$^{177}$$Lu reaction. However, radioisotopes with higher specific radioactivity are required in the field of radioimmunotherapy using labeled monoclonal antibodies. Thus, an alternative production route, namely the $$^{176}$$Yb(n,$$gamma$$)$$^{177}$$Yb $$rightarrow$$ $$^{177}$$Lu process was studied to produce no-carrier-added (nca) $$^{177}$$Lu in this work. The radiochemical separation of the nca $$^{177}$$Lu from the macroscopic ytterbium target was investigated by means of reversed-phase ion-pair HPLC. The nca $$^{177}$$Lu was obtained in radiochemical pure form with a separation yield of 80%.

Journal Articles

Production of positron emitters of metallic elements to study plant uptake and distribution

Watanabe, Satoshi; Ishioka, Noriko; Osa, Akihiko; Koizumi, Mitsuo; Sekine, Toshiaki; Kiyomiya, Shoichiro*; Nakanishi, Hiromi*; Mori, Satoshi*

Radiochimica Acta, 89(11-12), p.853 - 858, 2002/02

 Times Cited Count:17 Percentile:74.85(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Production of radio isotopes in JAERI

Isotope News, (3), p.2 - 5, 1981/00

no abstracts in English

Journal Articles

History of some important RI -Co-60-; Review

Genshiryoku Kogyo, 22(5), p.19 - 22, 1976/05

no abstracts in English

Oral presentation

Production of $$^{67}$$Cu for cancer therapy using fast neutrons from $$^{nat}$$C(d,n) reaction

Hashimoto, Kazuyuki; Kawabata, Masako; Saeki, Hideya; Tsukada, Kazuaki; Sato, Nozomi*; Motoishi, Shoji*; Nagai, Yasuki; Watanabe, Satoshi; Ishioka, Noriko

no journal, , 

Copper-67 is an attractive radionuclide for cancer therapy, because of emissions of medium energy $$beta$$ particle (a mean energy of 141 keV) and $$gamma$$ rays (91, 93, 185 keV) suitable for imaging, and its appropriate half-life (62 hours). However, the use of $$^{67}$$Cu for clinical researches has been limited due to the difficulty in obtaining sufficient quantities. In this study, we have investigated the production of $$^{67}$$Cu by the $$^{68}$$Zn(n,x)$$^{67}$$Cu reaction (x = n'p, d) using fast neutrons from $$^{nat}$$C(d,n) reaction. The highly purified $$^{67}$$Cu was obtained by the two columns separation method (chelate resin chelex-100 and anion exchange resin AG1-X8). Furthermore, the labelling of DOTA and TETA which are useful bifunctional ligands for the labelling monoclonal antibodies was succeeded in more than 97% yield.

Oral presentation

Production of $$^{64}$$Cu and $$^{67}$$Cu for cancer diagnosis and therapy using accelerator neutrons

Hashimoto, Kazuyuki; Kawabata, Masako*; Nagai, Yasuki

no journal, , 

no abstracts in English

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

RI production by using accelerator neutrons at the Japan Atomic Energy Agency

Nagai, Yasuki

no journal, , 

no abstracts in English

Oral presentation

Development of liquid Bi target for continuous production of therapeutic radionuclide astatine-211, 3; Compatibility of candidate materials of the target window with high temperature liquid bismuth

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

no journal, , 

Four types materials (the reference material incl.) were selected as the candidate materials for target windows where high corrosion resistance is expected in high temperature liquid bismuth. In this paper, results of the corrosion test for the these candidate materials in stagnant bismuth at 500$$^{circ}$$C for 500 hours.

Oral presentation

Development of liquid Bi target for continuous production of therapeutic radionuclide astatine-211, 1; Liq. Bi target project overview

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

no journal, , 

This paper reports the project overview of a liquid bismuth target development for the continuous and large-scale production of astatine-211 ($$^{211}$$At), which is a promising next-generation cancer medicine to be administered to the body.

Oral presentation

Development of liquid Bi target for continuous production of therapeutic radionuclide astatine-211, 2; Irradiations to the liquid bismuth target

Watanabe, Shigeki*; Kondo, Hiroo*; Koka, Masashi*; Takai, Toshihide; Furukawa, Tomohiro; Ishioka, Noriko*

no journal, , 

In order to evaluate the usefulness as a target for astatine-211 ($$^{211}$$At) production, a helium beam irradiation test was performed on a liquid bismuth target. This paper reports the results of the qualitative and quantitative analyses of radioactive isotopes generated in the target and the radiation distribution.

Oral presentation

Development of liquid Bi target for continuous production of therapeutic radionuclide astatine-211, 4; Corrosion behavior of candidate materials for the target window in liquid bismuth under low oxygen partial pressure

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

no journal, , 

The authors report the result of corrosion test in stagnant bismuth at 500$$^{circ}$$C for 500 hrs under a low oxygen partial pressure for the target window that is expected to have high corrosion resistance in high-temperature liquid bismuth.

22 (Records 1-20 displayed on this page)