NEUTRON RADIOGRAPHY SYSTEM COLLIMATOR DESIGN VIA MONTE CARLO CALCULATION
Neutron radiography uses the unique interaction probabilities of neutrons to create images of materials. This imaging technique is non-destructive. MCNP Monte Carlo Code has been used to design an optimized neutron radiography system that utilizes 241 Am-Be neutron source. Many different arrangements have been simulated to obtain a neutron flux with higher amplitude and more uniform distribution in the collimator outlet, next to image plane. In the final arrangement the specifications of neutron filter, Gamma-ray shield and beam collimator has been determined. Simulations has been Carried out for a 5Ci 241 Am-Be neutron source. In this case 43.8 n/cm 2 s thermal neutron flux has been achieved at a distance of 35cm from neutron source.
Hamid Jafari Majid Shahriari
Department of Radiation Application Shahid Beheshti University Tehran, IRAN
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-4
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）