Developing a new transportation container for bulk irradiation source

Year
2016
Author(s)
Zhuang Dajie - China Institute for Radiation Protection
Li Guoqiang - China Institute for Radiation Protection
Wang Renze - China Institute for Radiation Protection, Taiyuan, China
Sun Hongchao - China Institute for Radiation Protection
Meng Dongyuan - China Institute for Radiation Protection
File Attachment
F2014.pdf552.25 KB
Abstract
For irradiation source supply and recycle to the irradiation station both at home and abroad, irradiation source will be transport from production site(Beijing) to irradiation station, as well as from irradiation station to waste repository. China Institute for Radiation Protection(CIRP) was commissioned the work of developing FCTC10 container. FCTC10 container is designed to transport Co-60 special form radioactive sources used in irradiation industry by road, railway or water. With a loading of 180 000 Ci Co-60, the package is a Type B(U), Category III (yellow) package and TI(Transport Index) 9.8. The design life is 20 years. FCTC10 package should comply with the requirements stipulated in IAEA regulations for the transportation of radioactive materials. The container consists of shielding container, hanging basket, protective cover and bracket. The shielding performance mainly rely on the shielding container, which comprises stainless steel shells, tungsten alloy and lead filling. And the structural and thermal integrity under the hypothetical accident conditions has been demonstrated through a series of analyses and test.