Worker Radiation Exposure during Transportation of Irradiated LEU Targets in a Typical MTR Reactor

Abstract

The paper estimates the radiation dose exposure for the worker in the second Egyptian research reactor ETRR-2 during the process of transporting the irradiated low enriched uranium LEU plates from the core to the hot cell. The aim of estimating the radiation doses distribution is determining the exposure dose for the worker during the transportation process as a safety point of view. In order to estimate irradiated LEU plates radiation doses, the MicroShield code has been used. The calculations show that the worker will receive radiation dose exposure within the permissible dose limits by controlling of time of exposure during the transporting LEU plates inside the hot cell.

Keywords: radiation exposure, dose calculation, radiation protection, transport of radioactive material.

Cite this Article

Amr Abdelhady. Worker Radiation Exposure during Transportation of Irradiated LEU Targets in a Typical MTR Reactor. Journal of Nuclear Engineering & Technology. 2020; 10(3): 52–58p.