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کلمات کلیدی: MCNP
موارد یافت شده: 37
1 - دز سنجی BCA (چکیده)2 - دز سنجی پرتوهای مصنوعی در محیط زیست با استفاده از کد MCNP (چکیده)
3 - استفاده از ید125برای براکی تراپی تومورهای مغزی (چکیده)
4 - Optimization of Body Composition Analyzer Facility, Considering Operator Dosimetry (چکیده)
5 - Hybrid Phantom Applications to Nuclear Medicine (چکیده)
6 - تعیین سطح مقطع های ماکروسکوپی پراکندگی و جذب نمونه های همگن مجهول (چکیده)
7 - Momte Carlo simulation of pulse pile-up effect in gamma spectrum of a PGNAA system (چکیده)
8 - Designation of the Best Shield for Detectors in IVNAA Setup and its Effects on Reducing Absorbed Doze (چکیده)
9 - Estimation of Absorbed and Effective Doses on the Different Body Organs from Monoenergetic Neutron Source (10-9MeV-20MeV) Based on the ORNL Analytical Adult Phantom (چکیده)
10 - بررسی و تحلیل انواع حفاظ آشکارساز در چیدمان IVNAA و تعیین حفاظ بهینه (چکیده)
11 - Which factors affect on Estimation of absorbed dose and effective dose (چکیده)
12 - Calculation of the radiochromic film type MD-55-1 response to gamma sources by (چکیده)
13 - Monte Carlo Calculation of Relative Dose Distribution and Dosimetry Parameters for an 192Ir Source in a Water Phantom Using MCNP4C (چکیده)
14 - محاسبه طیف انرژی نوترونهای سریع حاصل از واکنشهای (p,n) با استفاده از کد MCNPX و مقایسه با اندازه گیریهای تجربی (چکیده)
15 - بررسی اثر زاویه آشکارساز و پرتوهای گسیلی از چشمه Am-241 با سطح خاک در سامانه مین یاب طراحی شده براساس پس پراکندگی پرتوهای گاما (چکیده)
16 - Calculation of neutron self-shielding factor and its effect on estimating amount of sample matter in LS-PGNAA (چکیده)
17 - Activation rate uniformity in a bilateral IVNAA facility for two anthropomorphic phantoms (چکیده)
18 - Investigation of Activation Rate Uniformity in aPrompt-γ Rays IVNAA Facility (چکیده)
19 - BENCHMARKING OF THE MCNP CODE FOR DOSE ESTIMATION ACCURACY FROM INTERNAL PHOTON SOURCES IN ORNL ANALYTICAL PHANTOMS AT VARIOUS AGES (چکیده)
20 - Improvement the uniformity of the gamma production rate distribution with depth in a large biological sample for an IVNAA facility (چکیده)
21 - SURFACE EFFECT CORRECTION OF MOISTURE DETERMINATION BY NEUTRON PROBE USING PSO TECHNIQUE AND MCNP (چکیده)
22 - Improvement the uniformity of the gamma production rate distribution with depth in a large biological sample for an IVNAA facility (چکیده)
23 - Determination of Neutron Detectors Shield Used for the Detection of Landmines (چکیده)
24 - Optimization of a Detector Collimator for Use in a Gamma-Ray Backscattering Device for Anti-Personal Landmines Detection (چکیده)
25 - Evaluation of specific absorbed fractions from internal photon sources in ORNL analytical adult phantom (چکیده)
26 - Evaluation the nonlinear response function of a 3*3 in NaI scintillation detector for PGNAA applications (چکیده)
27 - Improving the safety of a body composition analyser based on the PGNAA method (چکیده)
28 - Shielding studies on a total-body neutron activation facility (چکیده)
29 - The effect of source shield on landmine detection (چکیده)
30 - Response Function of a 3×3 in. NaI Scintillation Detector in the range of 0.081 to 4.438 MeV (چکیده)
31 - Gamma Shielding Design Studies on 252Cf and 241Am-Be Neutron Sources (چکیده)
32 - Reduction of the Gamma Dose Equivalent due to 252Cf and 241Am-Be Neutron Sources in the Patients Soft Tissues When Using Body Chemical Composition Analyzer Bed (چکیده)
33 - Neutron spectrum measurements from 1-16 MeV in beryllium assemblies with a central D-T neutron source (چکیده)
34 - Low-energy neutron flux measurement using a resonance absorption filter surrounding a lithium glass scintillator (چکیده)
35 - The investigation of Am - Be neutron source shield effect used on landmine detection (چکیده)
36 - Monte Carlo simulation of electron transport in metallic and biological materials (چکیده)
37 - Proper shielding for NaI (Tl) detectors in combined neutron-g fields using MCNP (چکیده)
