Evaluation of Neutron Dose Rate Generated from Cf-252 Source Based on Theoretical Calculation Model
Evaluation of Neutron Dose Rate Generated from Cf-252 Source Based on Theoretical Calculation Model Pham Dang Quyet1*, 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 […]
Authors
- Trịnh Thị Tú Anh
- Pham Dang Quyet
Publication Details
- Journal
- International Journal of Science Architecture Technology and Environment
- Published
- 2025-11-08
- DOI
- https://doi.org/10.63680/ijsate1125023.021
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00