Journal of Radiation Research and Radiation Proces ›› 2018, Vol. 36 ›› Issue (2): 20601-020601.

### MCNP simulation and analysis of radiation fields in radioactive source storehouses in a certain university

YAN Xuewen, XUE Xiangming, YANG Xue, MA Yuefeng

1. China Institute for Radiation Protection, Taiyuan 030006, China
• Received:2017-12-18 Revised:2018-02-28 Online:2018-04-20 Published:2018-04-19

Abstract:

This study was to estimate the radiation field distribution and maximum storage capacity of a certain university's storehouse of radioactive sources without on-site detection, to provide optimized suggestions for radiation protection. The radiation field of the university's storehouse was simulated using Monte Carlo N particle transport code (MCNP) simulations, and compared with experimental values to verify the reliability of the simulation. The results revealed a difference of approximately 10% between the MCNP-simulated and experimentally measured values. Thus, our simulations were observed to provide relatively accurate estimations of the radiation field distribution and maximum storage capacities. The advantage of using MCNP simulations to estimate the radiation field in storehouses of radioactive sources and their surroundings lies in the fact that they enable one to effectively obtain the dose distribution at any point without entering the radiation field. The protective measures taken by our university ensure that the dose rate is less than the standard permissible limit at any point of concern. The maximum storage capacities for 137Cs and 60Co are estimated to be 4.88×1013Bq and 9.99×1010Bq, respectively.

CLC Number:

• TL77