نمایش نتایج جستجو برای
کلمات کلیدی: MCNP code
موارد یافت شده: 15
1 - Calibration Constant of a Silver Activated Geiger Counter Used for Neutron Efficiency Measurements in Plasma Focus Devices: Theoretical vs. Experimental Studies (چکیده)2 - Comparison of Radon (222Rn) and Thoron (220Rn) Gamma Dosimetry in the Environment Using the ORNL Mathematical Phantom (چکیده)
3 - دز سنجی پرتوهای مصنوعی در محیط زیست با استفاده از کد MCNP (چکیده)
4 - Momte Carlo simulation of pulse pile-up effect in gamma spectrum of a PGNAA system (چکیده)
5 - Monte Carlo Calculation of Relative Dose Distribution and Dosimetry Parameters for an 192Ir Source in a Water Phantom Using MCNP4C (چکیده)
6 - Calculation of neutron self-shielding factor and its effect on estimating amount of sample matter in LS-PGNAA (چکیده)
7 - Activation rate uniformity in a bilateral IVNAA facility for two anthropomorphic phantoms (چکیده)
8 - Optimization of a Detector Collimator for Use in a Gamma-Ray Backscattering Device for Anti-Personal Landmines Detection (چکیده)
9 - Evaluation the nonlinear response function of a 3*3 in NaI scintillation detector for PGNAA applications (چکیده)
10 - The effect of source shield on landmine detection (چکیده)
11 - Response Function of a 3×3 in. NaI Scintillation Detector in the range of 0.081 to 4.438 MeV (چکیده)
12 - Low-energy neutron flux measurement using a resonance absorption filter surrounding a lithium glass scintillator (چکیده)
13 - The investigation of Am - Be neutron source shield effect used on landmine detection (چکیده)
14 - Monte Carlo simulation of electron transport in metallic and biological materials (چکیده)
15 - Proper shielding for NaI (Tl) detectors in combined neutron-g fields using MCNP (چکیده)
