CASK DESIGN FOR THE SAFE TRANSPORT OF CO IRRADIATION UNIT ANDSPENT FUEL FROM ETRR-2 RESEARCH REACTOR

摘要

MCNP and ORIGEN II codes were used to determine gamma ray dose-rates outside two casks whichhave been used to transport radioactive 60Co and spent fuel from the ETRR-2 research reactor. Both,shielding and criticality calculations were performed to ensure safe transport of radioactive materials.