Implementation of the Protection Optimization for Normalization of Radiation Conditions in BSKH-3A

Abstract

The radiation conditions in the dry-storage block for spent nuclear fuel BSKh-3A was characterized by a high dose rate and allowed only brief admission of workers. The plan to normalize the radiation conditions included repeat replacement of workers, whose individual dose limit has been exhausted, and on the whole did not conform to the principle of protection optimization. Analysis of the design and radiation state of BSKh-3A has shown that possibilities for reducing the worker dose do exist. At the stages of current planning and actual performance of the work, it was possible to make changes in the technology used in the work, reduce labor costs, and add and optimize additional protection. As a result, the work was performed in accordance with the radiation safety norms and regulations, worker replacement was not required, and the collective dose was reduced more than 20-fold compared with the nominal level.