مقالات Radiation Physics and Engineering، دوره 5، شماره 11.Computational investigation of ۱ up to ۳ kCi Co-۶۰ source production at external irradiation boxes of TRR core using MCNPX code FullText2.Benchmark MCNP computer code simulation results against experimental data of neutron flux and spectrum from neutron imaging system of Tehran research reactor FullText3.A review of advanced Small Modular Reactors (SMRs) through a developed PIRT methodology FullText4.Investigation and Simulation of Gamma-Neutron Shielding for Nuclear- Pumped Lasers FullText5.The new design of heavy concrete as neutron and gamma shield using galena, B۴C, and nanomaterials FullText6.Experimental study on Fricke gelatin gel dosimeters FullText7.Analysis of the control rod withdrawal speed impact on the transient behavior of Bushehr-۱ NPP using Simulink software FullText8.Stability of PVA Fricke gel as a radiochromic indicator for blood irradiation FullTextتاریخ نمایه سازی مقالات: 16 دی 1402 - تعداد نمایش اطلاعات ژورنال: 104 آرشیو سال 1403 Radiation Physics and Engineeringدوره: 5شماره: 4دوره: 5شماره: 3دوره: 5شماره: 2دوره: 5شماره: 1آرشیو سال 1402 Radiation Physics and Engineeringدوره: 4شماره: 4دوره: 4شماره: 3دوره: 4شماره: 2دوره: 4شماره: 1آرشیو سال 1401 Radiation Physics and Engineeringدوره: 3شماره: 4دوره: 3شماره: 3دوره: 3شماره: 2دوره: 3شماره: 1آرشیو سال 1400 Radiation Physics and Engineeringدوره: 2شماره: 4دوره: 2شماره: 3دوره: 2شماره: 2دوره: 2شماره: 1آرشیو سال 1399 Radiation Physics and Engineeringدوره: 1شماره: 1دوره: 1شماره: 2دوره: 1شماره: 3دوره: 1شماره: 4