Area 2 Posters
Title |
Abs No |
Poster PDF / Full Paper |
Validation of Linac Bunker Shielding Calculations |
P02.01 |
|
Dose Enhancement in Thin Layers of Skin-Equivalent Material Caused by Photons and Electrons: A Monte-Carlo Study Using MCNP |
P02.02 |
|
Radiometric Characterization of High Background Radiation Areas (HBRA): Some Results from Kenya |
P02.03 |
|
QA/QC programme in use at UPSR/ITN |
P02.04 |
|
Environmental Monitoring at ITN with Passive Detectors: Comparison of the Symmetrical and Traditional TLD Holders |
P02.05 |
|
Detailed Dose Rate Measurements On Ruthenium-106 (Ru106) Eye Plaque Treatment Using An Anthropomorphic Rando Phantom |
P02.06 |
|
Resolving Ambiguity in Individual Dose Measurement with Dosemeters Calibrated in Terms of Different Quantities |
P02.07 |
|
Investigation into the Variability of Dose Measurement using a Selection of Approved Dosimetry Services |
P02.08 |
|
European Population Dose From Radiodiagnostic Procedures - Results Of DOSE DATAMED 2 |
P02.09 |
|
An Evaluation of the Equivalent Dose due to Natural Radioactivity in the Soil Around the Consolidated Tin Mine in Bukuru-Jos, Nigeria. |
P02.10 |
|
Investigation of Life Dose of Workers at Different Occupational Groups in Planned Exposure Situations in Iran |
P02.11 |
|
A Passive Radiation Dosemeter for Environmental Photon and Beta Monitoring |
P02.12 |
|
TLD Doses Investigation around Container/Vehicle Inspection System |
P02.13 |
|
Reproducibility of 3DCRT Isodose Curves Evaluation Obtained Using Spherical Fricke Xylenol Gel Phantom |
P02.14 |
|
Characterization of Optically Stimulated Luminescence Response of LiF:Mg,Ti and microLiF:Mg,Ti Dosimeters for Beta Radiation |
P02.15 |
|
Assessment of Dose and Optimization of Image Quality in the XVI Cone Beam CT System |
P02.16 |
|
Cosmic Radiation Monitoring for RAF Aircrew |
P02.17 |
|
Applicability of CaSO4:Eu,Ce Detectors in Personal Dosimetry |
P02.18 |
|
Evaluation Of Patient Radiation Dose And Risk Estimation During Orthopedic Surgery |
P02.19 |
|
Experimental Determination of the 3-D Photon Dose Rate Field in the Airspace Above the Chernobyl New Safe Confinement Constructi |
P02.20 |
|
The Process For The Approval Of UK Dosimetry Services |
P02.21 |
|
Occupational Radiation Exposures in Medicine and Industry in Poland |
P02.22 |
|
OSL of Personal Belongings and In Vivo Materials and their Potential use in Accidental Dosimetry |
P02.23 |
|
Retrospective Dose Estimation of Fetus from Radiological and Nuclear Medicine Examinations |
P02.24 |
|
ORAMED Recommendations to Reduce Medical Staff Exposure in Interventional Radiology and Cardiology |
P02.25 |
|
Efficiency of Radon Remediation in Swedish Houses |
P02.26 |
|
Nuclear Power Plant Data Analysis for InLight LDR Model 2 Dosimeter |
P02.27 |
|
Occupational Radiation Exposure Trends In Whole Body Dosimetry - Hp(10) |
P02.28 |
|
Clinical Application of GAFCHROMIC EBT Film for in Vivo Dose Measurements from Total Body Irradiation |
P02.29 |
|
Retrospective Dose Assessment In A Radiation Mass Casualty By EPR And OSL In Mobile Phones |
P02.30 |
|
Development of a Double Dosimetry Algorithm for Assessment of Effective Doses to Staff in Interventional Radiology |
P02.31 |
|
Patient Dose Research in Interventional Radiology Suites in Rio de Janeiro, Brazil |
P02.32 |
|
Radiation Dose To The Eyes Of Readers At The Least Distance Of Distinct Vision For Normal Eye From Nigerian Newspapers |
P02.33 |
|
Study Of Different PADC Materials With Regard To Sensitivity And Background |
P02.34 |
|
Comparison of Passive and Active Neutron Dosemeter Measurements around a Spent Fuel Cask |
P02.35 |
|
Neutron dosimetry around GUINEVERE |
P02.36 |
|
Analysis of Photon Energy Distribution at the Working Places in Nuclear Power Plants and Application to Lead Vest Shielding |
P02.37 |
|
Personal Dosimetry Management A Nuclear Industry Good Practice Guide |
P02.38 |
|
Preliminary Study of Dose Estimation Using Fingernail/EPR and OSL Method |
P02.39 |
|
Dose Conversion Coefficients for Pediatric CT Body Procedures based on Specific Sizes: Optimizing Radiation Protection of Saudi Children |
P02.40 |
|
Risk of Radiation Exposure of the Lens of the Eye for Members of the Public |
P02.41 |
|
Retrospective Dose Reconstruction Using Household Salt |
P02.42 |
|
Application of in-situ gamma-ray spectrometry to assess the concentrations of 40K, 238U and 232Th and mean annual effective dose rate levels in the several United Arab Emirates cities. |
P02.43 |
|
Assessment of Occupational Dose Records in a Radiopharmaceutical Facility |
P02.44 |
|
Trends in Occupational Exposure at Different Practices in a Nuclear Facility |
P02.45 |
|
Estimation of Whole Body Effective Dose in the Cardiac Catheter Laboratory: An Intercomparison of Currently Recommended Monitoring Strategies |
P02.46 |
|
Study of Radon Exhalation Rate from Soil and Rock Samples and Gamma Exposure rate in Chamaraja Nagar District, India |
P02.47 |
|
Population Doses from Medical Diagnostic X-ray Exposure in Belgium |
P02.48 |
|
A Discussion on the Number of Age-specific Phantoms Practically Needed for External Exposure to Gamma rays |
P02.49 |
|
CT Patient Dose Monitoring Using Radiochromic Dosimeters |
P02.50 |
|
Patient Dose Assessments in Diagnostic Radiology Employing Electronic Examination Records |
P02.51 |
|
Occupational Dosimetry During Intra-Procedure Placement And Removal Of Ru106 Brachytherapy Sources For The Treatment Of Choroidal Melanoma |
P02.52 |
|
Type Testing Of A Harshaw™ Ext-Rad Extremity Dosemeter With PTFE Filter For Measuring Dose To The Lens Of The Eye In Terms Of Hp(3) |
P02.53 |
|
Patient Organ Dose From CT Scan Examinations In Elven State Owned Hospitals Of Khorasan Province-Iran |
P02.54 |
|
Enhanced Local Radiation Injury from Encapsulated Sources |
P02.55 |
|
Criticality Accident Dosimetry: Harwell experiences with a Criticality Accident Dosimetry User Group |
P02.56 |
|
In situ Measurement of Outdoor Gamma Radiation Level in Redemption Camp, Ogun State, Nigeria |
P02.57 |
|
Dose Measurements of a Dental CBCT in Comparison with a 4 row MSCT and a Panoramic Device. |
P02.58 |
|
Exposure Measurements on Portable X-Ray Fluorescence Spectrometers |
P02.59 |
|
Dose Estimation of the Radiation Workers in the Cyclotron and PET/CT Center |
P02.60 |
|
Establishment of National Dose Reference Levels (DRLs) for Dental Radiology Practices at the UAE |
P02.61 |
|
Estimating the Doses for the Workers of a PET Radiopharmaceutical Production Facility |
P02.62 |
|
Estimation of Finger Doses Resulting from Laboratory Use of Beta Emitting Radionuclides |
P02.63 |
|
Estimating the Effective Dose Equivalent During Transport Radioactive Material Using the Two Dosimeter Approach |
P02.64 |
|
Evaluation of Photoneutron Activation and Radiological Impact Induced from a Medical Linear Accelerator |
P02.65 |
|
Estimation of Effective and Equivalent Dose Rates for Submersion in a Semi-Infinite Radioactive Cloud based on ICRP 107 and 110 |
P02.66 |
|
A Dosimetric Reconstruction Simulation Code Based On Geant4 and Voxel Phantom for Radiological External Photon Exposure Accident |
P02.67 |
|
A Study on the Annual Doses Received by the Workers of some Medical Practices |
P02.68 |
|
A Bayesian Analysis of Uncertainties on Lung Doses Resulting from Occupational Exposures to Uranium |
P02.69 |
|
Study of Dose Variation in Bladder and Rectum due to Positional Variation of Applicator in HDR Intracavitory Brachytherapy. |
P02.70 |
|
Radioactivity of Bottled Drinking Water and Consequent Dose Exposure to Consumers in Ondo State. Nigeria. |
P02.71 |
|
Practical Recommendations to Occupational Health Services of Nuclear Facilities for Monitoring of Internal Exposure to Radionuclides |
P02.72 |
|
Measurements of Uranium Radionuclides in Urine Samples and Internal Dose Assessments for the Personnel of Uranium-Mining Industry in Ukraine |
P02.73 |
|
Application of Radiotherapeutic Fixation Tools to Achieve Patient Setup Reproducibility during in vivo Gamma Spectrometry Investigation |
P02.74 |
|
A Bayesian Method for Identifying Occupational Intakes for Uranium Workers |
P02.75 |
|
Dose Assessment Due to Inhalation of Plutonium Nanoparticles |
P02.76 |
|
Dosimetry Of Natural Uranium Exposure By Integrating Alimentary Uranium Contribution To Bioassay Measurements |
P02.77 |
|
A Comparison of True Alpha Activities in Air Filter Samples with Values Obtained from Radioactivity-in-air Monitors |
P02.78 |
|
Estimated Thyroid Doses for Cohort Members of Epidemiological Study of Thyroid Cancer among Belarusian Children Exposed after the Chernobyl Accident |
P02.79 |
|
Thyroid Doses due to Iodine-131 Intakes among Chernobyl Clean-up Workers |
P02.80 |
|
Biokinetic Models for Pregnant and Lactating Woman: Adaptation of ICRP Models for Epidemiological Studies of Exposed Southern Urals Populations. |
P02.81 |
|
Validation of the Monte Carlo Simulation of HPGe Detector Using Point Like Source and the Homemade Emma Phantom |
P02.82 |
|
Uranium & Dosimetry in Aquatic Organisms: Which Isotopes & Descendants to Consider? |
P02.83 |
|
Dose Estimation Method of the Public after the Reactor Severe Accidents in Fukushima |
P02.84 |
|
GuiAR: A New Tool for Implementation IDEAS Guidelines |
P02.85 |
|
Inhalation, Intravenous and Wound Exposure to Am-241: A Comparison of Unperturbed Biokinetics |
P02.86 |
|
Determination of Actinides in Excreta by Alpha Spectrometry: Method Validation and Uncertainty Estimation |
P02.87 |
|
Measurement of Urine Radioactivites for the Internal Exposure of the Workers in the Hospitals |
P02.88 |
|
Air Sampling Measurement of a Working Condition for the Internal Exposure of the Workers in the Hospitals |
P02.89 |
|
Estimated Average Annual Exposure to Background Radiation inside the Hospital and Health Centers of Erbil city and its impact |
P02.90 |
|
Predictive Model of Aerosol Transport and Deposition. Application and Validation to the PWR Reactor Building |
P02.91 |
|
Radiation Dose Assessment of Consumer Products Containing Tritium |
P02.92 |
|
Evaluation of Internal Exposure of Nuclear Medicine Staff Working with Radioiodine and Technetium |
P02.93 |
|
Radionuclides Incorporated by Inhabitants of Surrounding Brazilian Uranium Mines |
P02.94 |
|
The Assessment of Internal Doses for the Korean Nuclear Medicine Workers based on the Thyroid Bioassay Measurement of I-131 |
P02.95 |
|
Effect of Change of Biokinetic Models on Interpretation of Bioassay Data |
P02.96 |
|
Study of the Influence of Radionuclide Biokinetics Distribution in Human Body on the Efficiency Response of Lung Counters |
P02.97 |
|
Element Transfer from Intake to Excretion in Human Body of Chinese adult men |
P02.98 |
|
Eurados Network on Internal Dosimetry |
P02.99 |
|
Quantitative Plutonium Microdistribution In Liver Of MAYAK Radiochemical Plant Workers |
P02.100 |
|
Uranium Concentrations in Natural Water Around Mysore City, India |
P02.101 |
|
Content of Uranium in Urine of Uranium Miners in Relation to Personal Dosimetry of Long Lived Alpha Radionuclides. |
P02.102 |
|
Assessment, using Monte Carlo and Biokinetic Models, of the Absorbed Dose in the Thyroid, as a Critical Organ, in Scintigraphies with I-123 and Tc-99m |
P02.103 |
|
Controlling Radiological and Chemical Intakes of Uranium in the Workplace: Applications of Biokinetic Modeling and Occupational Monitoring Data |
P02.104 |
|
WBC IRSN 2011 Intercomparison: Participation Of The ISPRA Joint Research Centre WBC Laboratory |
P02.105 |
|
Implementation of an Intercomparison Exercice according to ISO/IEC 28218 in the Internal Dosimetry Services of Spanish Nuclear Power Plants |
P02.106 |
|
Results of Internal Monitoring for Nuclear Medicine Workers in the City of Medellin, Colombia |
P02.107 |
|
New Dose Factors for Ingestion of 131I |
P02.108 |
|
Dose Coefficients For Incorporation Of Lead, Bismuth And Polonium |
P02.109 |
|
Human Hair as Biomonitor of Chronic Intake of Uranium: Studies at a Nuclear Fuel Fabrication Plant. |
P02.110 |
|
Determination of urine biological exposure index for the monitoring of uranium chemical toxicity |
P02.111 |
|
Simulation of Auger Electron Emission Spectra for 99mTc and 123I by Validated Monte Carlo Codes |
P02.112 |
|
Internal Dose Assessment of 177Lu-DOTA-SP for Quantification of Arginine Renal Protection Effect |
P02.113 |
|
Internal Dose Assessment of 177Lu-DOTA-SP for Quantification of Arginine Renal Protection Effect |
P02.114 |
|
Ingestion dose coefficient update and uncertainty assessment in biokinetic and dosimetric models of α-, β-, αγ- and βγ-emitter |
P02.115 |
|
Characteristics of a Thyroid Spectrometer Based on a LaBr3(Ce) Detector |
P02.116 |
|
A Model of Plutonium Metabolism for Reconstruction of Doses for the Mayak Workers Based on the Autopsy Data |
P02.117 |
|
Carbon-14 Dosimetry and the Latest Evidence for the Biological Half Life of Carbon-14 Radiolabelled Compounds |
P02.118 |
|
Biokmod Application for the Evaluation of Different Types of Bioassays |
P02.119 |
|
Therapeutic Intervention Decision for Tritium Uptake within Limit |
P02.120 |
|
The Experimental Basis for Revising Particle Clearance from the Extra-Thoracic and Bronchial Regions in the Revised ICRP Human Respiratory Tract Model |
P02.121 |
|
The Effect of Radiological Protection Policies and Work Programme on Radiological Measurements at the Dounreay Site. |
P02.122 |
|
Pregnancy and Lactation as a Factor of Increased Accumulation of Bone-seeking Radionuclides in Maternal Body |
P02.123 |
|
Estimates Of Effective Doses Among Czech Uranium Miners |
P02.124 |
|
Effect of Respiratory Motion on Counting Efficiency Using a 4D NURBS-Based Cardiac-Torso (NCAT) Phantom |
P02.125 |
|
HOTDOSE: A Software Package to Calculate Dose Probability Distributions for Hot Particle Inhalation |
P01.126 |
|
Natural Radiation Exposure from Indoor Radon and Thoron in China |
P02.127 |
|
Dose Coefficients For Beta Decay, By Incorporation By Ingestion Using The "Human Alimentary Tract Model",According To ICRP 100. |
P02.128 |
|
NATO Biodosimetry Exercise - Inter-Assay Comparison - |
P02.129 |
|
Developing Biological Dosimetry Laboratory for the Assessment of Radiation Overexposure in Saudi Arabia |
P02.130 |
|
The Uptake Kinetics Of Ba-133 And Heavy Metals (Co, Cr, Cd And Pb) In The Gibraltar Strait Marine Waters |
P02.131 |
|
Strategy for Validation of External Doses for Techa Riverside Residents |
P02.133 |
|
Biomedical Evaluation of a Radiological Incident - A Bayesian Approach for Presenting Uncertainty on Biological Dose Estimates |
P02.134 |
|
Biological Dosimetry for Occupational Overexposure: Some changes in Operation Concept |
P02.135 |
|
New Concepts for Modelling Pu/Am Decorporation by DTPA |
P02.136 |
|
MADORTools For Managment Of Internan Contamination By Actinides And DTPA Therapy |
P02.137 |
|
Conceptual Structure of Java-oriented Environment for Modeling Biokinetics of Incorporated Radionuclides and Internal Dose Calculations |
P02.138 |
|
Microdosimetric Assessment of the Cellular Responses to Low-Dose Exposure |
P02.139 |
|
Time-dependent Gene Expression Analysis in Human Peripheral Blood Lymphocytes for Biodosimetric Applications after Low and High Dose Gamma-Irradiation |
P02.140 |
|
RENEB – Realizing The European Network In Biological Dosimetry |
P02.141 |
|
Approaches of the Cytigenetical Dose Evaluation of the Irradiation Nonuniformity |
P02.142 |
|
Monitoring Of Capillaries In Occupational Exposure As Biological Indicator In Radiation Protection |
P02.143 |
|
Nanohybrids composed of quantum dots and enzyme as photocatalysts induced by gamma rays |
P02.144 |
|
Performance of the automated dicentric and cytokinesis block micronucleus assays in a recent NATO exercise of established biodosimetry methods |
P02.145 |
|
The Probability of Radiation-induced Damage of Macromolecules with Complex Spatial Structure |
P02.147 |
|
Establishment Of A Dose-Response Curve Of 60Co Gamma-Ray Irradiation By Dicentric Chromosome Analysis |
P02.148 |
|
Validation Method of Biological Dosimetry in an Accreditation Process |
P02.149 |
|
ESR dosimetry study of workers from Stepnogorsk uranium processing plant, Kazakhstan |
P02.150 |
|
Patient Dose Measurements in Digital Mammography, Using Computed Radiography (CR) Versus Dose in Analog Mammography |
P02.151 |
|
Computer Simulations and Image Reconstruction for a Proton Computed Tomography System |
P02.154 |
|
Mass Attenuation Coefficients of X-rays in ISO Quality Concrete in Barite of Different Regions of Brazil |
P02.155 |
|
Comparison of Different Methods for Measuring CT Dose Profiles with a New Dosimetry Phantom |
P02.156 |
|
Using MCA DigiDART for Neutron Detection |
P02.157 |
|
First Argentinean Intercomparison of Neutron Detectors |
P02.158 |
|
Thin Wall Recombination Chamber Filled with Nitrogen |
P02.159 |
|
Radioactive Source Detection by Vehicle Radiation Portal Monitors Considering the Background Suppression |
P02.160 |
|
Strontium-90 in the Teeth of Residents of Techa Riverside Settlements |
P02.161 |
|
Study of the Triage Method for Radiological Mass Casualty Event Using Plastic Scintillator |
P02.162 |
|
Mathematical Calibrations for Measurements of Radionuclides in People following a Radiological Incident |
P02.163 |
|
Mobile Unit for Site Characterization in Environmental Remediation Projects |
P02.164 |
|
Analysis of the Life Time of Quartz TL peaks: Comparison of the Deconvolution Using the First Order Kinetic to the Initial Rise |
P02.165 |
|
Which Levels of Alpha- and Beta Contamination on Surfaces are Possible to Detect with Manual Search? |
P02.166 |
|
Fiber Optic Interferometric Sensor for Registration of X-Ray Radiation |
P02.168 |
|
Angular Response of Polymer Films Irradiated with Accelerated Electron Beam |
P02.169 |
|
Studying the Variation of Radon Level Among Covering Materials in Some Houses in Major Cities of the Southwestern Nigeria |
P02.171 |
|
Evaluation and Analytical Comparison of Different 2D and 3D Radiotherapeutic Treatment Planning Systems using Dosimetry with Anthropomorphic Phantom |
P02.175 |
|
Development of a Protocol for Radiation Survey Meter Calibration |
P02.177 |
|
Characterization of OSL response of LiF:Mg,Ti and microLiF:Mg, Ti in 60Co gamma source |
P02.179 |
|
Long Distance Radiation Monitoring System using Optical Fiber Scintillator and Silicon Photomultiplier |
P02.180 |
|
Phenomenon of Self-Absorption of Calcium Sulfate - Dysprosium Dosimeter, Made With Iranian Natural Calcium Sulfate |
P02.181 |
|
A Comprehensive Study Of The Glandular Dose To Women Participating In The National Mammography Program For Early Detection Of Cancer Of The Breast, In Israel. |
P02.182 |
|
Different Methods for Tritium Determination in Surface Water by LSC |
P02.183 |
|
Full-range isotopic calibration of an RMS detector by F-18 decaying source method |
P02.184 |
|
Criteria For Reporting Radiological Data: Two Different Approaches |
P02.185 |
|
Thermal Neutron Fluence Measurements Arround a Cyclotron for PET producion |
P02.186 |
|
Identification of a Low-Energy Beta-Emitter by High-Resolution Gamma Spectrometry |
P02.187 |
|
The use of a TrueBeam System for the Characterisation of Optical Fibre Based Dosimeters |
P02.188 |
|
Neutron Dosimetry Device Using PADC Nuclear Track Detectors |
P02.189 |
|
Review on Adequacy of Skin Exposure Dose Evaluation Using Harshaw Algorithm |
P02.190 |
|
Enhancement of Exposure Dose Prediction Reliability for Radiation Workers by Using Represented TLD/ADR Ratio |
P02.191 |
|
Can GATE Be Used For Monte Carlo Calibrations Of Whole Body Counters? |
P02.192 |
|
Easy Determination of the State of Contamination with a GM Counter |
P02.193 |
|
Building a Modular γ-Radiation Monitoring System from off the Shelf Components |
P02.194 |
|
Stability of a Berthold LB6411 Neutron Probe for Use as a Secondary Standard |
P02.195 |
|
Uncertainty of Fragment Yield Ratios from Heavy Ion Fragmentation Measured with Track-Etched Detectors |
P02.196 |
|
Performance Evaluation of Silicon Photomultiplier Sensor for Thickness Gauge |
P02.197 |
|
Thermoluminescence Characteristics of High Gamma Dose Irradiated Natural Quartz |
P02.198 |
|
Deconvoluting the Internal Contamination of the LaBr3:Ce Crystal |
P02.199 |
|
Interlaboratory Comparison of Tritium Electrolytic Enrichment Systems at RBI (Zagreb) and JSI (Ljubljana) |
P02.200 |
|
The "Electronic Instrumentation Laboratory" (Label) of the Radiation Protection Sector at the Joint Research Centre of ISPRA |
P02.201 |
|
Reducing Personnel Doses and Ensuring Radiation Protection: Electronics Calibration and Performance Checks in the Joint Research Centre Of ISPRA |
P02.202 |
|
Determination of the Effective Linear Attenuation Coefficient of Samples with Unknown Chemical Composition |
P02.203 |
|
Application of Neutron Fields with Fractional Changes of Fast and Thermal Neutron to Test Neutron Measuring Devices |
P02.204 |
|
Maintenance of the Buried Neutron Irradiator |
P02.205 |
|
Evaluation of Radiation Exposure by Natural Radionuclides for Employees in Water Supplies |
P02.206 |
|
Setup and Characterization of X-ray Reference Calibration Fields in a Dosimetry Laboratory |
P02.207 |
|
Towards a Tool for an Automatic Evaluation of Mammographic Image Quality |
P02.208 |
|
Development of High Performance Automated Digital Imaging Microscope and Counting System Applied For Etched Track Detectors |
P02.209 |
|
Evaluation of Novel Formulations of PADC Using the TASLImage Analysis System |
P02.211 |
|
Study of Agate Using the OSL Technique and Application in High Dose Dosimetry |
P02.212 |
|
Development and Implementation of the NDS Next Generation Thermoluminescence Dosimetry Service |
P02.213 |
|
Characteristics of Teflon Powder for Thermoluminescent Dosimetry |
P02.214 |
|
An Innovative Electronic Detector for Computed Tomography Dosimetry |
P02.215 |
|
Mass Attenuation Coefficients of X-rays in Calcium Phosphate Biomaterials |
P02.216 |
|
Establishment of Radiation Measurement Instrument Calibration Facility Capable of Lowering Scattered Radiation and Shielding Background Radiation |
P02.217 |
|
Mean glandular dose behavior using different glandularity phantoms |
P02.218 |
|
Simultaneous Determination of U and Pu Isotopes by Alpha Spectrometry |
P02.220 |
|
Study of the Response of a SP9 Neutron Detector to an Am-Be Source |
P02.221 |
|
New image analysis system for nuclear track detector Radon dosimeter, developed in the Central Laboratory of the Italian Red Cross (SMRA/LC/CRI). |
P02.222 |
|
NaI spectrometers for indirect detection of neutrons |
P02.223 |
|
Using the Image Pro Plus to Count Alpha Particles Tracks in Cr-39 |
P02.224 |
|
International Intercomparison of Thoron Active Devices with NIRS Thoron Chamber |
P02.225 |
|
Mercury Supplementary Inner Shield for Low-Background Gamma-Ray Spectrometry |
P02.226 |
|
Introducing Monte Carlo based calibrations at the whole body counter of the Swedish Radiation Safety Authority |
P02.227 |
|
Development of a New Iodine Monitor |
P02.228 |
|
On The Counting Parameters In The Alpha/Beta Gas Flow Proportional Counters |
P02.229 |
|
The Response of Radiophotoluminescent Glass Dosimeter for Charged Particles and Its Microscopic Consideration |
P02.230 |
|
Environmental Dosimetry with the Pille TL Space Dosimetry System During the BEXUS-12 Stratospheric Balloon Flight |
P02.231 |
|
Stability Study of Ionization Chambers in Standard Mammography Radiation Beams |
P02.232 |
|
Application of Monte Carlo efficiency transfer method to calibration of coplanar-grid large volume CZT detector |
P02.233 |
|
A Sample Assay Geometry for a Wide Range of Sample Types and Volumes with a Single Efficiency Calibration, and Still Achieve Reasonable Accuracy |
P02.234 |
|
Investigation of the Dosimetric Parameters of the PorTL Thermoluminescent Dosimetry System |
P02.235 |
|
Luminescence Technique and Research on OSL Measurement Instrument |
P02.236 |
|
Investigation of Metrological Characteristics of Whole Body Spectrometer |
P02.237 |
|
Automation of the Calibration of Dosimeters for Radiotherapy |
P02.238 |
|
Performance and type testing of selected dosimeter used for individual monitoring |
P02.239 |
|
Conversion Factors of Modern Devices Which Can Be Used to Measure Radioactivity in Human Thyroids after Radiation Accident |
P02.240 |
|
New Electronic Personal Dosimeter |
P02.241 |
|
Determination of the I-131 Activities in Thyroids from Measurements of Exposure Rates after the Chernobyl Accident: Devices Response and Uncertainties |
P02.242 |
|
Neutron Spectrometry and Dosimetry Results at McMaster KN Accelerator Using Three Different Instruments |
P02.243 |
|
Application of the OSL Technique for Determination of the Useful Calibration Distance Ranges for Beta Radiation Detectors |
P02.245 |
|
Calibration of 90Sr+90Y Sources used for Betatherapy, using a Postal Kit of Thermoluminescent Dosimeters |
P02.246 |
|
Extensions to the Beta Secondary Standard BSS 2 |
P02.247 |
|
Life Cycle Assessment of the Romanian Reference Standard for Dosimetric Quantities |
P02.248 |
|
The Effect of the Radiation Background on the Accuracy of the Calibration Performed with Gamma Ray in the IFIN-HH |
P02.249 |
|
Establishment of the Practical Peak Voltage for Tomography Standard Radiation Qualities at the Calibration Laboratory of IPEN |
P02.250 |
|
Evaluation of Gamma Dose Rate Probes Response in the Slovenian Early Warning System |
P02.251 |
|
Establishment of the New IEC 61267 Mammography Qualities in a Clinical System |
P02.252 |
|
Results of a Dosimetric System for Personal Dose Equivalent Assessment. |
P02.253 |
|
Conversion Coefficients from Air Kerma to Personal Dose Equivalent for Low Energy X-Ray Reference Radiations |
P02.254 |
|
Application of advanced composite materials in the creation of reference volume sources of radionuclides activity. |
P02.255 |
|
Accreditation of Laboratories in the Field of Radiation Science in Croatia |
P02.256 |
|
Experience Of Introducing A Personal Dosimetry Website HPA Dosimetry On-Line |
P02.257 |
|
Progress in Neutron Metrology and Dosimetry at the National Physical Laboratory, London, UK |
P02.258 |
|
Photon Radiation from the 252Cf and 241Am-Be Neutron Sources of the PSI Calibration Laboratory |
P02.259 |
|
Novel Reference Field for Pulsed Photon Radiation for Research and Type Testing |
P02.260 |
|
The effect of PMMA Build-up Layer for a Calibration of Dosemeter for Gamma-ray Sources |
P02.261 |
|
Calibration of the High and Low Resolution Gamma-Ray Spectrometers |
P02.262 |
|
Evaluation of Radiation Dose in Computed Tomography Standard Beams Using Simulators |
P02.263 |
|
Impact Of IEC 61066:2006 Standard Testing To The Joint Research Centre Dosimetry System |
P02.264 |
|
Assessment of the Uncertainty of the Results of Control of an Individual Dose Equivalent |
P02.265 |
|
Evaluation Methodology And Performance Tests Of Ionization Chambers Of The Air Kerma Area Product Using Mathematical Simulation |
P02.266 |
|
Upgrading of the National Radiation Standards at the Secondary Standards Dosimetry Laboratory (SSDL) in the Philippines |
P02.267 |
|
The Support Offered by the Romanian Primary Activity Standard Laboratory to the Nuclear Medicine Field |
P02.268 |
|
Calibration and Energy Response Determination of Radiation Protection Area Survey Meters in ISO Narrow Spectrum Photon Beams |
P02.269 |
|
Secondary Standard Dosimetry Laboratory in Central Laboratory for Radiological Protection in Poland |
P02.270 |
|
Measurement of Single Scan Dose Profiles in Computed Tomography Dose Phantom Using a Micro Ionization Chamber |
P02.271 |
|
Electronic Dosemeters in Pulsed Fields of Ionising Radiation: Determination of Relevant Parameters to Decide on Usability |
P02.272 |
|
Calculation of dose distribution in PET/CT units using MCNPX monte Carlo code |
P02.273 |
|
Determination of the Radiation Field in an Interim Storage Facility |
P02.274 |
|
Construction and use of a Library of 25 Full-Body Male Numerical Models: Rationale and Results |
P02.275 |
|
Use of Computer Vision Algorithms for Fast Evaluation of the Dose Caused by Scattered Radiation in Industrial Environment |
P02.276 |
|
Monte Carlo Analysis of Spectrum Produced by Transmission-type X-ray Target |
P02.277 |
|
Monte Carlo Modeling of Photon Dose Rate Field in the Chernobyl New Safe Confinement |
P02.278 |
|
Analysis of Dose and Risk Associated with the use of Transmission X-Rays Body Scanner Using Monte Carlo Simulation |
P02.279 |
|
Selection of an Appropriate Air Kerma Rate Constant for Volumetric Se-75 Sources |
P02.280 |
|
Radiological Dose Exposure comparison study between Monte Carlo codes MCNP and SCALE |
P02.281 |
|
Simulation of the Influence of the ISO Water Slab Phantom on the Neutron Field of a Calibration Source |
P02.282 |
|
Monte Carlo Simulation of Radiation Leakage and Design Optimisation for Doors and Doorframes of X-Ray Facilities |
P02.283 |
|
Comparison of Radiation Shielding Requirements for Ir-192, Co-60 and Yb-169 HDR Brachytherapy Sources Using Monte Carlo Simulations |
P02.284 |
|
Calculation of Calibration Factors and Minimum Detectable Activities in the Lung of Radionuclides Released in the Case of a Nuclear Power Plant Accident |
P02.285 |
|
Thyroid Screening Of Members Of The Public With Portable NaI Detectors After A Radionuclide Release From A Nuclear Power Plant |
P02.286 |
|
Transformation of the Normal Distribution for Monte Carlo modeling of regions of Adult trabecular bones for use in Computational Models of Exposure |
P02.287 |
|
Measurements of Air Kerma as function of potential in X-ray tubes for estimates standard quantities used for dosimetric evaluation |
P02.288 |
|
Review of Dosimetric Models of the Extrathoracic Airways for Internal Photon Emitters |
P02.289 |
|
Experimental Verification of TPS Software and Tabulated Data for Blocked Fields |
P02.290 |
|
The Interaction of Natural Background Gamma Radiation with Depleted Uranium Micro-Particles Located Deep in the Human Body |
P02.291 |
|
Shielding Evaluation for a Radiotherapy Bunker by NCRP 151 and Portuguese Regulation on Radiation Safety |
P02.292 |
|
Quantification of the Effect of Respiratory Motion on Efficiency Calibration for Internal Dosimetry |
P02.293 |
|
Comparison Between Simulation and Measurement of Activation Products in High-Energy Medical Linear Accelerators |
P02.294 |
|
Proton Beam Characterization Using Monte Carlo Simulation Technique |
P02.295 |
|
Modeling of Spontaneous Particle Sputtering from Plutonium Dioxide Material |
P02.296 |
|
Dose Rate Distribution from a Standard Waste Drum Arrangement |
P02.297 |