نمایش نتایج جستجو برای
کلمات کلیدی: Neutron
موارد یافت شده: 90
1 - Neutron pumping of active medium formed by gadolinium isotopes 155Gd and 156Gd pair: A feasibility study (چکیده)2 - Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor (چکیده)
3 - Neutron spectroscopy with TENIS using an artificial neural network (چکیده)
4 - Self-similar behavior of the neutron fracture functions (چکیده)
5 - Landmine-identification system based on the detection of scattered neutrons: A feasibility study (چکیده)
6 - Gadolinium neutron capture therapy: Calculation of 157Gd kerma factor and a dosimetry study using MCNP Monte Carlo code (چکیده)
7 - Dosimetric evaluation of neutron contamination caused by dental restorations during photon radiotherapy with a 15 MV Siemens Primus linear accelerator (چکیده)
8 - Computational assessment of the cellular dosimetry and microdosimetry of the gadolinium electrons released during neutron capture therapy (چکیده)
9 - Experimental study of the influence of dental restorations on thermal and fast photo-neutron production in radiotherapy with a high-energy photon beam (چکیده)
10 - Study of Photoneutron Production for the 18 MV Photon Beam of the Siemens Medical linac by Monte Carlo Simulation (چکیده)
11 - TENIS — ThErmal Neutron Imaging System for use in BNCT (چکیده)
12 - Neutron yield and energy spectrum of 13C(alpha,n)16O reaction in liquid scintillator of KamLAND: A Nedis-2m simulation (چکیده)
13 - Hydrogen-bond directionality and symmetry in [C(O)NH](N)2P(O)-based structures: a comparison between X-ray crystallography data and neutron-normalized values, and evaluation of reliability (چکیده)
14 - A multi-moderator neutron spectrometer for use in BNCT studies of the Tehran research reactor (چکیده)
15 - Neutron beam preparation for soil moisture measurements: Nedis-PHITS and artificial neural networks study (چکیده)
16 - Nedis-Serpent simulation of a neutron source assembly with complex internal heterogeneous structure (چکیده)
17 - Boron Neutron Capture Therapy for Breast Cancer during Pregnancy: A Feasibility Study (چکیده)
18 - Conceptual design for a new heterogeneous 241Am-9Be neutron source assembly using SOURCES4C-MCNPX hybrid simulations (چکیده)
19 - Optimization of pulse processing parameters for digital neutron-gamma discrimination (چکیده)
20 - A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics (چکیده)
21 - A neutron scattering soil moisture measurement system with a linear response (چکیده)
22 - Compact stars in energy-momentum squared gravity (چکیده)
23 - Designing the proper neutron shield for patients undergoing the radiotherapy with high-energy linacs (چکیده)
24 - Characterization of a new shielding rubber for use in neutron–gamma mixed fields (چکیده)
25 - Digital neutron-gamma discrimination in a wide energy range using pulse reconstruction method (چکیده)
26 - Replacement of Bonner spheres with polyethylene cylinders for the unfolding of an 241Am–Be neutron energy spectrum (چکیده)
27 - A photon transport model code for use in scintillation detectors (چکیده)
28 - Calibration Constant of a Silver Activated Geiger Counter Used for Neutron Efficiency Measurements in Plasma Focus Devices: Theoretical vs. Experimental Studies (چکیده)
29 - A simple well-logging tool using boronlined sodium iodide scintillators and an 241Am-Be neutron source (چکیده)
30 - A comparative study on neutron-gamma discrimination with NE213 and UGLLT scintillators using zero-crossing method (چکیده)
31 - Neutron-gamma discrimination with UGAB scintillator using zero-crossing method (چکیده)
32 - Lightguide influence on timing response of scintillation detectors (چکیده)
33 - Modelling NE213 scintillator response to neutrons using an MCNPX-PHOTRACK hybrid code (چکیده)
34 - Modelling boron-lined proportional counter response to neutrons (چکیده)
35 - On timing response improvement of an NE213 scintillator attached to two PMTs (چکیده)
36 - NE213/BC501A scintillator−lightguide assembly response to 241Am−Be neutrons: An MCNPX−PHOTRACK hybrid code simulation (چکیده)
37 - Design and Fabrication of a Data Acquisition System for Pulsed Neutron Flux Measurement of Plasma Focus Devices (چکیده)
38 - A Compton-suppression detection system for use in manganese bath measurements (چکیده)
39 - Speyer (چکیده)
40 - A plastic scintillator-based 2D thermal neutron mapping system for use in BNCT studies (چکیده)
41 - Digital neutron-gamma discrimination with scintillators: An innovative approach (چکیده)
42 - Determination of neutron fracture functions from a global QCD analysis of the leading neutron production at HERA (چکیده)
43 - 3D imaging of elemental concentration associated with malignant tumor in breast cancer using Neutron Stimulated Emission Computed Tomography: a Monte Carlo simulation study (چکیده)
44 - Stable solitary waves in super dense plasmas at external magnetic fields (چکیده)
45 - Depth dose evaluation for prostate cancer treatment using boron neutron capture therapy (چکیده)
46 - Head on collision of shock and breaking waves in degenerate hadronic plasmas (چکیده)
47 - Neutron spectrometry and determination of neutron contamination around the 15 MV Siemens Primus LINAC (چکیده)
48 - A Monte Carlo study for photoneutron dose estimations around the high-energy linacs (چکیده)
49 - Utilization of 241Am-9Be Neutron Source in PGNAA Setup Used in Cement Raw Material Analysis (چکیده)
50 - A Monte Carlo Study of the Influence of Neutron Source Spectrum on PGNAA Facility Performance in Cement Raw Material Analysis (چکیده)
51 - Assessment of neutron shielding effect on photoneutron dose reduction produced in high-energy linear accelerator (چکیده)
52 - Shielding optimization in an in vivo activation analysis setup (چکیده)
53 - Finding a suitable shield for mixed neutron and photon fields based on an Am–Be source (چکیده)
54 - The measurements of thermal neutron flux distribution in a paraffin phantom (چکیده)
55 - Facility optimization to improve activation rate distributions during IVNAA (چکیده)
56 - A Novel Neutron Dosimeter (چکیده)
57 - Different effective dose conversion coefficients for monoenergetic neutron fluence from 10-9 MeV to 20 MeV – A methodological comparative study (چکیده)
58 - Quantifying the geometry correction factor and effectiveness (چکیده)
59 - Investigations on landmine detection by BF3 detector (چکیده)
60 - Electron Mobility Calculation in GaAs and the Effects of Fast Neutron Radiation on its Crystal Structure (چکیده)
61 - طراحی هم خط ساز بهینه برای دستگاه IVNAA (چکیده)
62 - دز سنجی BCA (چکیده)
63 - تخمین دز موثر کل بدن در هندسه های متفاوت دزیمتری با استفاده از دزیمتری نوترون (چکیده)
64 - Review on Fast Neutron Therapy (چکیده)
65 - Designing and Optimization of Neutron Dosimeter (چکیده)
66 - Neutrons applications in cancer treatment and in specific diagnostics (چکیده)
67 - Development of a Bonner sphere spectrometer with emphasis on decreasing the contribution of scattering by using a new designed shadow cone (چکیده)
68 - MEASUREMENT OF THE NEUTRON SPECTRUM BY THE MULTI-SPHERE METHOD USING A BF3 COUNTER (چکیده)
69 - Evaluation of response matrix of a multisphere neutron spectrometer with water moderator (چکیده)
70 - Comparison of low field electron transport characteristics in Ge and Si semiconductors and effects of neutron energy deposition on their crystal structure (چکیده)
71 - Calculation of Low Field Electron Transport Characteristics in Ge and Effects of Fast Neutron Radiation on its Crystal Structure (چکیده)
72 - 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)
73 - Which factors affect on Estimation of absorbed dose and effective dose (چکیده)
74 - IMPROVING THE PERFORMANCE OF 241Am-Be FOR PGNAA APPLICATIONS USING A PROPER SHIELDING FOR NEUTRON SOURCE AND THE NaI DETECTOR (چکیده)
75 - Calculation of neutron self-shielding factor and its effect on estimating amount of sample matter in LS-PGNAA (چکیده)
76 - SURFACE EFFECT CORRECTION OF MOISTURE DETERMINATION BY NEUTRON PROBE USING PSO TECHNIQUE AND MCNP (چکیده)
77 - Theoretical Calculation of Atom Displacement Damage in Wurtzite GaN Crystal Structure by Fast Neutron Radiation (چکیده)
78 - Determination of Neutron Detectors Shield Used for the Detection of Landmines (چکیده)
79 - Experimental optimization of a landmine detection facility using PGNAA method (چکیده)
80 - The soil moisture and its effect on the detection of buried hydrogenous material by neutron backscattering technique (چکیده)
81 - Improving the moderator geometry of an anti-personnel landmine detection system (چکیده)
82 - An Optimum Landmine Detection System Using Polyethylene Moderator and 241Am-Be as a Neutron Source (چکیده)
83 - Evaluation the nonlinear response function of a 3*3 in NaI scintillation detector for PGNAA applications (چکیده)
84 - The safety of a landmine detection system using graphite and polyethylene moderator (چکیده)
85 - Shielding studies on a total-body neutron activation facility (چکیده)
86 - Gamma Shielding Design Studies on 252Cf and 241Am-Be Neutron Sources (چکیده)
87 - Assessment of neutron fluence to organ dose conversion coefficients in the ORNL analytical adult phantom (چکیده)
88 - Structure and vibrational assignment of the enol form of 1,1,1-trifluoro-2,4-pentanedione (چکیده)
89 - Proper shielding for NaI (Tl) detectors in combined neutron-g fields using MCNP (چکیده)
90 - a comparison of neutron spectrum unfolding codes used with a miniature ne213 detector (چکیده)
