Characterization of Radio-Waste from TRIGA II Research Reactor and Assessment of Corresponding Radiation Dose in Bangladesh

Abstract

: During the reactor operation a significant amount of high and intermediate level radioactive wastes are inevitably raised, which are managed and finally disposed of with particular care. The ion exchange resin is used to purify water during the operation of 3 MW TRIGA Mark II research reactor in Bangladesh, when the decontamination efficiency is insufficient to maintain the required primary coolant quality. Five spent ion exchange resin samples and eleven liquid samples from exhausted coolant of 3 MW TRIGA Mark II research reactor were analyzed by using HPGe detector having 40% relative efficiency and 1.8 keV resolution coupled with computer-based MCA. Two radionuclides 54 Mn, 60 Co have been recognized in the spent ion-exchange resin and three radionuclides such as 137 Cs, 60 Co, and 65 Zn have been identified in the liquid radio wastes samples. The specific activity concentrations of these nuclides and the Inhalation dose for the corresponding nuclide for different body parts such as bladder, Bone surface, Brain, Breast, Stomach, Kidneys, Liver, Red Marrow, lungs, Skin and Thyroid for public are also evaluated according to the ICRP 68. Rad Toolbox software was used for the assessment. The maximum inhalation dose is originated from 137 Cs and lung is found to be the maximum radiation sensitive organ, received maximum dose of 53.5 m Sv from 60 Co (1332 keV). The experiment results would be helpful to develop a policy for radioactive waste management that produced during the operation and maintenance of a research reactor.