Radiological aspects in the production and transport of a radioactive iridium source from the reactor to the industrial user

Bhabha Atomic Research Centre (BARC) and the organization the Board of Radiation and Isotope Technology (BRIT) handles hundreds of kilo Curies in shielded and contained facilities under safe procedures to supply ¹⁹²Ir sources to industry in India and abroad. The starting point of the ¹⁹²Ir source begins from the inactive stage of ¹⁹²Ir pellet packing, irradiation in research reactor, fabrication and supply and ends in the hands of the industrial user who ultimately returns it to DAE after its useful life for removal/re-use or burial in the National Waste Repository. This paper looks at the radiological aspects of the entire process and the efforts in ensuring radiological safety. Based on the analysis of dose distribution in various operations, efforts are being made for further reduction of exposure associated with production and transport. A detailed dose analysis, shielding evaluation for ¹⁹²Ir during its handling in hot cell and transportation and its validation is detailed in the full text of the paper