نمایش نتایج جستجو برای
عنوان: neutron
نویسنده: میری حکیم آباد
موارد یافت شده: 31
1 - Modeling the adult female phantom in the supine and prone postures and initial dose assessment in breast cancer diagnosis with Neutron Stimulated Emission Computed Tomography (چکیده)2 - Depth dose evaluation for prostate cancer treatment using boron neutron capture therapy (چکیده)
3 - Neutron spectrometry and determination of neutron contamination around the 15 MV Siemens Primus LINAC (چکیده)
4 - Neural network unfolding of neutron spectrum measured by gold foil-based Bonner sphere (چکیده)
5 - A Monte Carlo study for photoneutron dose estimations around the high-energy linacs (چکیده)
6 - A study of the effect of the lung shape on the lung absorbed dose in six standard photon and neutron exposure geometries (چکیده)
7 - Boron Neutron Capture Therapy for Breast Cancer in Pregnancy: A Simulative Dosimetry Estimation Study (چکیده)
8 - Assessment of neutron shielding effect on photoneutron dose reduction produced in high-energy linear accelerator (چکیده)
9 - Finding a suitable shield for mixed neutron and photon fields based on an Am–Be source (چکیده)
10 - The measurements of thermal neutron flux distribution in a paraffin phantom (چکیده)
11 - The operator dose assessment of landmine detection systems using the neutron backscattering method (چکیده)
12 - A Novel Neutron Dosimeter (چکیده)
13 - Different effective dose conversion coefficients for monoenergetic neutron fluence from 10-9 MeV to 20 MeV – A methodological comparative study (چکیده)
14 - Review on Fast Neutron Therapy (چکیده)
15 - Designing and Optimization of Neutron Dosimeter (چکیده)
16 - Neutrons applications in cancer treatment and in specific diagnostics (چکیده)
17 - MEASUREMENT OF THE NEUTRON SPECTRUM BY THE MULTI-SPHERE METHOD USING A BF3 COUNTER (چکیده)
18 - Evaluation of response matrix of a multisphere neutron spectrometer with water moderator (چکیده)
19 - 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)
20 - IMPROVING THE PERFORMANCE OF 241Am-Be FOR PGNAA APPLICATIONS USING A PROPER SHIELDING FOR NEUTRON SOURCE AND THE NaI DETECTOR (چکیده)
21 - Calculation of neutron self-shielding factor and its effect on estimating amount of sample matter in LS-PGNAA (چکیده)
22 - Determination of Neutron Detectors Shield Used for the Detection of Landmines (چکیده)
23 - The soil moisture and its effect on the detection of buried hydrogenous material by neutron backscattering technique (چکیده)
24 - An Optimum Landmine Detection System Using Polyethylene Moderator and 241Am-Be as a Neutron Source (چکیده)
25 - Shielding studies on a total-body neutron activation facility (چکیده)
26 - Gamma Shielding Design Studies on 252Cf and 241Am-Be Neutron Sources (چکیده)
27 - 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)
28 - Neutron spectrum measurements from 1-16 MeV in beryllium assemblies with a central D-T neutron source (چکیده)
29 - Assessment of neutron fluence to organ dose conversion coefficients in the ORNL analytical adult phantom (چکیده)
30 - The investigation of Am - Be neutron source shield effect used on landmine detection (چکیده)
31 - Proper shielding for NaI (Tl) detectors in combined neutron-g fields using MCNP (چکیده)
