Survey of LEU based 99mTc generators loading process

99mTc is most commonly used as a radiopharmaceutical in the field of nuclear medicine, accounting for more than 80% of all diagnostic nuclear medicine procedure. The 99mTc is obtained from 99Mo, which is produced by fission of 235U ((n, f) method) and the neutron capture (n, γ) method using the 98Mo target. However, a supplying of 99Mo is only depends on imports from any other countries, so JAEA find a way out at domestic production of a part of 99Mo that (n, γ) method in cooperation with the industrial circles. On the other hand, INVAP has been working in the supply of 99Mo production facilities using LEU. This report provides descriptions the detail technical aspects related to the facility and operations for loading 99mTc generator. These key issues and technical provided in this report is believed to be useful for developing and updating them. (author)