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Journal Articles

Large scale production of $$^{64}$$Cu and $$^{67}$$Cu via the $$^{64}$$Zn(n, p)$$^{64}$$Cu and $$^{68}$$Zn(n, np/d)$$^{67}$$Cu reactions using accelerator neutrons

Kawabata, Masako*; Motoishi, Shoji*; Ota, Akio*; Motomura, Arata*; Saeki, Hideya*; Tsukada, Kazuaki; Hashimoto, Shintaro; Iwamoto, Nobuyuki; Nagai, Yasuki*; Hashimoto, Kazuyuki*

Journal of Radioanalytical and Nuclear Chemistry, 330(3), p.913 - 922, 2021/12

 Times Cited Count:7 Percentile:75.99(Chemistry, Analytical)

Both $$^{64}$$Cu and $$^{67}$$Cu are promising radionuclides in nuclear medicine. Production yields of these radionuclides were quantified by irradiating 55.4 g of natural zinc with accelerator neutrons. Clinically suitable $$^{64}$$Cu and $$^{67}$$Cu yields were estimated by experimental based numerical simulations using 100 g of enriched $$^{64}$$Zn and $$^{68}$$Zn, respectively, and elevated neutron fluxes from 40 MeV, 2 mA deuterons. A combined thermal- and resin-separation method was developed to isolate $$^{64}$$Cu and $$^{67}$$Cu from zinc, resulting in 73% separation efficiency and 97% zinc recovery. Such methods can provide large scale production of $$^{64}$$Cu and $$^{67}$$Cu for clinical applications.

Journal Articles

Mesoporous alumina-titania composites with enhanced molybdenum adsorption towards medical radioisotope production

Benu, D. P.*; Earnshaw, J.*; Ashok, A.*; Tsuchiya, Kunihiko; Saptiama, I.*; Yuliarto, B.*; Suendo, V.*; Mukti, R. R.*; Fukumitsu, Nobuyoshi*; Ariga, Katsuhiko*; et al.

Bulletin of the Chemical Society of Japan, 94(2), p.502 - 507, 2021/02

 Times Cited Count:11 Percentile:65.6(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

$$^{99}$$Mo yield using large sample mass of MoO$$_{3}$$ for sustainable production of $$^{99}$$Mo

Tsukada, Kazuaki; Nagai, Yasuki*; Hashimoto, Kazuyuki*; Kawabata, Masako*; Minato, Futoshi; Saeki, Hideya*; Motoishi, Shoji*; Ito, Masatoshi*

Journal of the Physical Society of Japan, 87(4), p.043201_1 - 043201_5, 2018/04

 Times Cited Count:10 Percentile:59.94(Physics, Multidisciplinary)

Journal Articles

New production method and applications of $$^{67}$$Cu suitable for both cancer diagnosis and therapy

Nagai, Yasuki*; Tsukada, Kazuaki

Isotope News, (753), p.28 - 32, 2017/10

no abstracts in English

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:77.83(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

Present status of radioisotope production for medical use with reactors and a cyclotron in JAERI

Proc. of Korea Atomic Industrial Forum,Inc., p.347 - 357, 1997/04

no abstracts in English

Journal Articles

Impression of Japan-Russia Seminar on Utilization of Radiation and Radioisotopes for Medical Purposes

Isotope News, 0(483), p.38 - 39, 1994/09

no abstracts in English

Oral presentation

Medical radioisotope production with accelerator neutrons by 40 MeV deuterons

Tsukada, Kazuaki; Sato, Nozomi; Watanabe, Satoshi; Ishioka, Noriko; Hatsukawa, Yuichi; Hashimoto, Kazuyuki; Kin, Tadahiro*; Kawabata, Masako; Saeki, Hideya; Nagai, Yasuki

no journal, , 

no abstracts in English

Oral presentation

Production of medical radioisotope $$^{90}$$Y with fast neutrons by the Be(p,n) reaction

Takeda, Shinsaku; Tsukada, Kazuaki; Sato, Tetsuya; Asai, Masato; Nagai, Yasuki; Sakama, Minoru*

no journal, , 

no abstracts in English

Oral presentation

Production and purification of medical radioisotope Y-90 with accelerator neutrons by deuterons

Tsukada, Kazuaki; Sato, Tetsuya; Hashimoto, Kazuyuki; Saeki, Hideya; Hatsukawa, Yuichi; Nagai, Yasuki; Watanabe, Satoshi; Ishioka, Noriko; Takeda, Shinsaku*

no journal, , 

A new system has been proposed for the generation of radioisotopes with accelerator neutrons by deuterons, especially the production of $$^{90}$$Y (T$$_{1/2}$$ = 64 h), which has been used for the nuclear medicine. Enriched $$^{90}$$Zr nitrate samples were irradiated with neutrons, which were obtained by the $$^{nat}$$C(d,n) using 40 MeV deuterons provided from the TIARA cyclotron. $$^{90}$$Y was successfully produced via the (n, p) reaction, and separated from the Zr nitrate target by three columns method with a hydrochloric acid. After the purification, a labelling of DTPA with $$^{90}$$Y had been performed. In this result, the yield was about 90% under $$>$$2.5 $$mu$$M of DTPA, although the yields were decreased at the DTPA concentration below 2.5 $$mu$$M.

Oral presentation

Medical radioisotope production with accelerator neutrons by deuterons

Tsukada, Kazuaki; Sato, Nozomi*; Watanabe, Satoshi; Ishioka, Noriko; Hatsukawa, Yuichi; Hashimoto, Kazuyuki; Kin, Tadahiro*; Takeda, Shinsaku*; Kawabata, Masako; Saeki, Hideya; et al.

no journal, , 

A new system has been proposed for the generation of radioisotopes with accelerator neutrons by deuterons, especially the production of Mo-99, Y-90, Cu-67, and Cu-64. Enriched Mo-100, Zr-90, Zn-68 and Zn-64 oxide samples were irradiated with neutrons, which were obtained by the $$^{nat}$$C(d,n) and Be(d,n) using 40 MeV deuterons provided from the TIARA cyclotron. Mo-99, Y-90, Cu-67, and Cu-64 were successfully produced via the (n, x) reactions, and we clearly observed the $$gamma$$-rays. Particularly, yields of impurity radionuclides were much smaller than that of Mo-99 and Cu-67, and therefore radioactive waste produced during chemical processing would be reduced compared with other proposed reaction systems. The present results demonstrate that the radioisotopes, Mo-99, Y-90, Cu-67, and Cu-64, can be produced by using fast neutrons, and strongly suggest that the reaction system is one of the most promising routes to produce high quality medical radioisotope.

Oral presentation

Evaluation for specific radioactivity of $$^{67}$$Cu for cancer therapy, produced with accelerator neutrons by deuterons

Hashimoto, Kazuyuki*; Kawabata, Masako*; Saeki, Hideya*; Sato, Shunichi*; Tsukada, Kazuaki; Sugo, Yumi*; Nagai, Yasuki*; Hatsukawa, Yuichi*; Ishioka, Noriko*

no journal, , 

no abstracts in English

Oral presentation

Measurement and estimation of the $$^{99}$$Mo production yield by the acceleration neutron

Tsukada, Kazuaki; Nagai, Yasuki*; Hashimoto, Kazuyuki*; Kawabata, Masako*; Minato, Futoshi; Saeki, Hideya*; Motoishi, Shoji*; Watanabe, Satoshi*; Ito, Masatoshi*

no journal, , 

no abstracts in English

Oral presentation

Production method development of cancer therapeutic $$^{67}$$Cu using thermoseparation for cancer therapy

Ota, Akio*; Kawabata, Masako*; Motoishi, Shoji*; Saeki, Hideya*; Hashimoto, Kazuyuki*; Tsukada, Kazuaki; Hatsukawa, Yuichi*; Nagai, Yasuki*

no journal, , 

$$^{67}$$Cu and $$^{64}$$Cu are recognized to be promising radioisotopes for cancer therapy and diagnosis in nuclear medicine. It is possible to produce both $$^{67}$$Cu and $$^{64}$$Cu using accelerator neutrons from the zinc sample with different isotopic enrichment level, therefore the same separation procedure can be applied for both radioisotopes. Three-step-column separation chemistry was previously reported to separate $$^{67}$$Cu from the irradiated zinc sample. This paper reports that newly developed thermo-separation system to remove the bulk zinc from the sample using a difference in vapor pressure between Zn and Cu.

Oral presentation

Production of Sc-47 for cancer therapy using accelerator neutrons

Tsukada, Kazuaki; Hashimoto, Kazuyuki*; Hashimoto, Shintaro; Asai, Masato; Hatsukawa, Yuichi*; Saeki, Hideya*; Kawabata, Masako*; Ota, Akio*; Motomura, Arata*

no journal, , 

no abstracts in English

Oral presentation

Medical RI production using domestic nuclear infrastructures for self-sustenance, 5; Ac-225 production using the experimental fast reactor Joyo

Sano, Aaru; Maeda, Shigetaka; Itagaki, Wataru; Sasaki, Shinji; Sasaki, Yuto*; Takaki, Naoyuki*

no journal, , 

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 medical research and economic security of Japan. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity 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. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.

Oral presentation

Medical RI production in existing reactors, 3; Comparison of medical RI production performances in Joyo and PWR

Takaki, Naoyuki*; Iwahashi, Daiki*; Sasaki, Yuto*; Maeda, Shigetaka

no journal, , 

We compared the production characteristics of Tc-99m and Ac-225 in the fast experimental reactor "Joyo" and commercial PWR, summarized the characteristics of each, and showed the possibility of domestic production of medical RI using domestic infrastructure.

Oral presentation

Reaction cross section models to estimate purity of medical $$^{177}$$Lu produced by deuterons

Hashimoto, Shintaro; Nagai, Yasuki*

no journal, , 

A plan by irradiating enriched $$^{176}$$Yb samples with accelerated deuterons has been considered to produce $$^{177}$$Lu, one of the medical radioisotopes. However, Lu isotopes other than $$^{177}$$Lu are produced by nuclear reactions between the deuteron and the other Yb isotopes included in the enriched Yb sample, and are impurities in the $$^{177}$$Lu product. In this study, we determined all reaction cross section models for Lu isotopes production by deuteron irradiation on Yb samples on the basis of experimental data of the Lu production cross section. By combining these models with the particle and heavy-ion transport code system, PHITS, we can evaluate the yield of each Lu isotopes produced and the purity of $$^{177}$$Lu nuclides when Yb samples with arbitrary composition ratios are irradiated with deuteron beams.

Oral presentation

Ac-225 production using the experimental fast reactor Joyo

Sano, Aaru; Sasaki, Yuto*; Sasaki, Shinji; Iwamoto, Nobuyuki; Ouchi, Kazuki; Kitatsuji, Yoshihiro; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

Ac-225 can be applied to cancer treatment of various sites, but world supply is scarce. In this study, in order to study the production of Ac-225 using fast neutrons, we evaluated the amount of Ac-225 produced by fast neutron irradiation of Joyo. Burn up calculations were performed with Ra-226 as the target using ORIGEN2.2 for the evaluation of the production amount. In addition, the uncertainty of Ac-225 production was evaluated from the nuclear reaction cross section of the target nuclide and the neutron flux of Joyo. This study showed that a large amount of Ac-225 can be produced by irradiating Ra-226 at Joyo. In the future, we will improve the accuracy of evaluation of the production amount through demonstration experiments.

Oral presentation

Domestic production of Mo-99 and Ac-225 using commercial PWR and fast experimental reactor Joyo

Takaki, Naoyuki*; Iwahashi, Daiki*; Sasaki, Yuto*; Maeda, Shigetaka

no journal, , 

The production technology of medical radioisotopes (RI) using existing nuclear fission reactors has been studied to improve/achieve their domestic preparedness in Japan. The target nuclides currently considered in our project are Mo/Tc which is the most commonly used ones in medical diagnosis and Ac-225 which is recently known as effective alpha emitting nuclide for targeted alpha-particle therapy. Existing fission reactors, PWRs and Joyo, have potentials to work as excellent facilities for medical isotope production, as by-products of heat/electricity generation without consuming electricity and need for new plant construction.

24 (Records 1-20 displayed on this page)