Radiological evaluation of an alternative path to transport cobalt device after irradiation in open pool type reactor-(another calculation (original) (raw)
This study suggests an alternative path to transport the cobalt device after irradiation in open-pool-type reactor from the reactor core to the cobalt cell. The cobalt transport process in current path depends on using heavy shielded cask, 1500 Kg weight, under water surface of spent fuel storage pool which may cause a missile impact of spent fuel accident (Falling of heavy load into spent fuel storage pool). To avoid using the shielded cask, an alternative path is suggested depending on transporting the cobalt device through the hot cells of the reactor; the testing and the cobalt cells. The expected radiation dose rate rise associated with the alternative transport path must be evaluated at positions which the worker will be found during transport process. SCALE/MAVRIC sequence code was used to determine the dose rate levels along the suggested transport path; over spent fuel storage pool water surface, and around testing and cobalt cells. The calculated results show rise in radiation dose levels more than the permissible dose rate limits around testing cell. Suggested procedures are presented in this study to decrease the received dose by worker found around testing cell during transport process.
Sign up for access to the world's latest research.
checkGet notified about relevant papers
checkSave papers to use in your research
checkJoin the discussion with peers
checkTrack your impact
Loading Preview
Sorry, preview is currently unavailable. You can download the paper by clicking the button above.
Loading Preview
Sorry, preview is currently unavailable. You can download the paper by clicking the button above.