Radiation Levels in Structural Components of Cirus Reactor—Estimation and Measurement

Abstract

Estimation of radioactivities and radiation levels is carried out for structural components of the Cirus reactor. The estimated results of radiation levels are compared with in situ measurements. The data will be useful for future decommissioning of Cirus reactor from the viewpoint of decontamination techniques, dose budgeting and waste management. Neutron fluxes were estimated in different structural components by considering the operational history of the reactor. The neutron fluxes in core and reflector regions were estimated by using computer code FINHEX. Point depletion computer code ORIGEN2 was used for carrying out activity calculations. The activities estimated by ORIGEN2 were used as input in point kernel computer code IGSHIELD for estimating radiation level.