V2I11P21

Evaluation of Neutron Dose Rate Generated from Cf-252 Source Based on Theoretical Calculation Model

Pham Dang Quyet^1*, Trinh Thi Tu Anh²

Abstract

Californium-252 (Cf-252) is a spontaneous fission radioactive source that is utilized in both scientific and industrial fields due to its strong neutron emission. The MCNP code is widely used for simulating dose rates and designing radiation shielding to protect against radiation emitted by various radioactive sources, including Cf-252. This method, however, requires some knowledge of MCNP simulation techniques and detailed data about the radioactive source and shielding materials. Therefore, in this study, we propose a theoretical calculation method to rapidly estimate the neutron dose rate along the central axis of the Cf-252 source. At the same time, a TPS-451c neutron dose meter was used to evaluate the theoretical model’s calculated values. The results show strong agreement between the experimental measurements and the theoretical calculations.

Keywords:

Neutron dose rate; Cf-252; TPS-451c; Theoretical calculation model