High thermo-separation efficiency of Tc from molten MoO samples by repeated milking tests

Nagai, Yasuki; Kawabata, Masako; Sato, Nozomi; Hashimoto, Kazuyuki; Saeki, Hideya; Motoishi, Shoji*

Journal of the Physical Society of Japan, 83(8), p.083201_1 - 083201_4, 2014/07

https://doi.org/10.7566/JPSJ.83.083201

ALICE predictions on the accelerator production of molybdenum-99

R.M.Lambrecht*; Sekine, Toshiaki; H.V.Ruiz*

Applied Radiation and Isotopes, 51(2), p.177 - 182, 1999/00

https://doi.org/10.1016/S0969-8043(98)00171-7

no abstracts in English

Radioisotope Production Centre, BATAN, Indonesia

*

Isotope News, 0(508), p.12 - 15, 1996/09

http://ci.nii.ac.jp/naid/10002586370

no abstracts in English

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

Status of Mo/Tc production development by (n,) reaction in JMTR

Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori

no journal, , 

Technetium-99m (Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce Mo by (n,) method, a parent nuclide of Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of Mo/Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on Mo/Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO pellets, (2) Separation and concentration of Tc by the solvent extraction from Mo solution, (3) Examination of Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of Mo/Tc production improvement.

Recovery and purification of Tc isolated from MoO3 using a thermal separation technique

Kawabata, Masako*; Hashimoto, Kazuyuki; Motoishi, Shoji*; Saeki, Hideya*; Shiina, Takayuki*; Ota, Akio*; Takeuchi, Nobuhiro*; Nagai, Yasuki

no journal, , 

no abstracts in English

Challenge for Mo-99/Tc-99m production by JRR-3

Chiba, Yusuke

no journal, , 

Japan depends on foreign countries for many medical isotopes, and in order to realize domestic production from the viewpoint of enhancing the security of the medical system, the Atomic Energy Commission formulated the "Action Plan for the Production and Use of Radioisotopes for Medical Purposes" on 2022. In this Action Plan, one of the goals is to "manufacture and supply approximately 30% of the domestic demand for Mo-99/Tc-99m by utilizing JRR-3". JRR-3 has several utilization facilities for neutron beam experiments, irradiation tests of reactor material, and manufacturing radio isotopes for medicine use and silicon semiconductor by transmutation. JAEA is aiming to establish production technology of Mo-99 by neutron capture method, making effective use of the performance of JRR-3. The demonstration test is scheduled to be completed in 2025, and the prospect for domestic production of Mo-99 is expected to be established. In this issue, we will introduce the current status of the test.