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Mirion Technologies provides products, services, and software that allow our customers to safely leverage the power of ionizing radiation for the greater good of humanity through critical applications in the medical, nuclear, defense markets, as well as laboratories, scientific research, analysis and exploration.

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Technical Papers

Mirion experts author technical and research papers on a wide variety of topics. Click a link below or use our search engine to locate a paper of interest. You will be linked to a downloadable PDF version.

Technical Papers

Spectroscopic noble gas stack monitor with continuous unattended operation and analysis
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Burn-up Credit Applications for UO2 and MOX Fuel Assemblies in AREVA/COGEMA
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CALIBRATION AND HOT TESTING OF THE ADVANCED NUCLEAR MEASUREMENT SYSTEMS USED FOR WASTE CHARACTERIZATION IN COGEMA'S NEW ACC COMPACTION FACILITY
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Comparison of Gamma and Passive Neutron Non-Destructive Assay Total Measurement Uncertainty Using the High Efficiency Neutron Counter
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AN OVERVIEW OF THE INTEGRATED CRATE INTERROGATION SYSTEM (ICIS) FOR USE AT THE SAVANNAH RIVER SITE
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An MCNP Based Method to Determine the Matrix Attenuation Correction Factors for a Gamma Box Counter
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INNOVATIVE NUCLEAR MEASUREMENT TECHNIQUES USED TO CHARACTERIZE WASTE PRODUCED BY COGEMA‘S NEW COMPACTION FACILITY
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DESIGN AND PERFORMANCE OF THE INTEGRATED WASTE ASSAY SYSTEM (IWAS)
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RADIONUCLIDE CHARACTERIZATION OF A PLUTONIUM-CONTAMINATED SHEAR-BALER
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Operator Experience Measuring Pu-bearing Waste at PNC Using the Waste Drum Assay System
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SMOPY a new NDA tool for safeguards of LEU and MOX spent fuel
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INTEGRATED WASTE ASSAY SYSTEM (IWAS) AND ANALYSIS ENHANCEMENTS
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THE USE OF THREE DEDICATED NUCLEAR MEASUREMENT TOOLS FOR D & D OPERATIONS IN NUCLEAR FACILITIES
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CANBERRA solutions for source location and activity determination for investigations of ORCADE dismantling project at AREVA NC La Hague site
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THE SPECIAL PROPERTIES OF MASSIMETRIC EFFICIENCY CALIBRATIONS AS COMPARED TO THE TRADITIONAL EFFICIENCY CALIBRATION FOR D&D AND ER GAMMA SPECTROSCOPY MEASUREMENTS – 10021
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NDA Analysis of Legacy INL Wastes for disposal at WIPP
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Rapid Gamma Screening of Shipments of Analytical Samples To Meet DOT Regulations
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The use of Segmented Silicon Drift Diodes (SSDDs) in Nuclear Identification Systems
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State-of-the art cryocooler solutions for HPGe detectors
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The Efficiency Characterization of Germanium Detectors at Energies less than 45 keV -- 10479
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A SEMI-EMPIRICAL FORMULA FOR REPRESENTING THE FULL ENERGY PEAK EFFICIENCIES OF PLANAR GE DETECTORS
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TCAM – Ruggedized CAM Detector
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ANSI N42.34 Testing of Canberra Hand-Held Identifiers
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EVOLUTION OF A HAND-HELD DEVICE FOR HOMELAND SECURITY PURPOSES
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Performance Characterization of A New Cam System
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THE USE OF IN SITU GAMMA SPECTROSCOPY TO SAVE TIME, DOSE, AND MONEY IN OPERATING NUCLEAR FACILITIES
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AN INVESTIGATION INTO THE USEFULNESS OF THE ISOCS MATHEMATICAL EFFICIENCY CALIBRATION FOR LARGE RECTANGULAR 3”x5”x16” NAI DETECTORS
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Probabilistic uncertainty estimator for gamma-spectroscopy measurements
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LabSOCS vs. SOURCE-BASED GAMMA-RAY DETECTOR EFFICIENCY COMPARISONS FOR NUCLEAR POWER PLANT GEOMETRIES
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Improved Detector Response Characterization Method in ISOCS and LabSOCS
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A new low-level Y-ray spectrometry system for environmental radioactivity at the underground laboratory Felsenkeller
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ASSAY ERRORS INTRODUCED BY MATRIX CORRECTION USING TRANSMISSIONS DETERMINED BY THE MATERIAL BASIS SET METHOD
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AUTOMATIC GAMMA SPECTROSCOPIC WATER MONITOR
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The Calculation of Self Attenuation Factors for Simple Bodies in the Far Field Approximation
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Comparison Of Neutron Coincidence And Multiplicity Counting Techniques For Safeguards
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COMPARISON OF THE PERFORMANCE OF DIFFERENT URANIUM ENRICHMENT ANALYSIS CODES USING A RANGE OF DETECTOR TYPES
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COMPARISON OF A VARIETY OF GAMMA ATTENUATION CORRECTION TECHNIQUES FOR DIFFERENT WASTE MATRICES
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A NUMERICAL APPROACH TO PU GAMMA-RAY SELF-ABSORPTION CORRECTION
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IN-LINE MONITORING OF RADIUM SLURRY BY GAMMA-RAY SPECTROMETRY
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DETECTION AND CORRECTION OF INHOMOGENEITIES IN DRUM WASTE ASSAY SYSTEMS
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Radioactive Waste Measurements: Contributors to Total Measurement Uncertainty
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An Investigation into the Limitations of Tomographic Scanning for Quantitative Non-destructive Gamma-ray Measurements of High Density Radioactive Waste
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The Impact of Matrix Heterogeneity on Gamma-Ray Waste Assay
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DEPENDENCE OF THE MGA CODE PERFORMANCE ON DETECTOR ENERGY RESOLUTION
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The Non Destructive Assay of Special Nuclear Materials in Different Physical Forms
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The Influence of Source and Matrix Nonuniformity on the TMU and Bias of Large Container Gamma-Ray Assay Results
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EVALUATING THE DEPENDENCE OF GAMMA-ASSAY RESULTS ON SOURCE AND MATRIX DISTRIBUTIONS
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Larger Volume Detector Efficiency Parameterization with the MGA Code
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Non Destructive Assay Box Counter
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Comparison of the Performance of Different Plutonium Isotopic Codes Using a Range of Detector Types
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PU-238 ASSAY PERFORMANCE WITH THE CANBERRA IQ3 SYSTEM
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Q2 - A VERY LOW LEVEL QUANTITATIVE AND QUALITATIVE WASTE ASSAY AND RELEASE CERTIFICATION
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The Next Generation Tomographic Gamma Scanner
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Total Measurement Uncertainty Estimation For Tomographic Gamma Scanner
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VALIDATION OF IQ3 MEASUREMENTS FOR HIGH-DENSITY LOW-ENRICHED-URANIUM WASTE DRUMS AT PELINDABA
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THE CALIBRATION OF SEGMENTED GAMMA SCANNERS USING ROD SOURCES
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THE ACCUSCAN-II VERTICAL SCANNING GERMANIUM WHOLE BODY COUNTER
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A COMPUTERIZED, ANTHROPOMETRICALLY DESIGNED, HIGH THROUGHPUT, WHOLE BODY COUNTER FOR THE NUCLEAR INDUSTRY
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AN EVALUATION OF RECENT TECHNOLOGY, INCLUDING BROAD ENERGY GERMANIUM DETECTORS (BEGE), EMPLOYED BY CANBERRA INDUSTRIES TO IMPROVE MEASUREMENT SENSITIVITIES OF RADIONUCLIDES DEPOSITED IN LUNGS
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A New 208 Liter Drum Neutron Coincidence Counter with Add-A-Source Matrix Correction
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The Absolute Calibration of Active Neutron Assay Instruments
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RESULTS OF LOW LEVEL WASTE ANALYSIS OF PLUTONIUM WITH A PASSIVE NEUTRON COINCIDENCE COUNTER
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Calibrating Passive Neutron Multiplicity and Waste Counters Using Calibrated 252Cf Sources: Estimating a Pu-Values Without Pu
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The Use of 252Cf for Calibrating Safeguards Monitors
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The Estimation of the Minimum Detectable Activity from Measured Passive Neutron Coincidence Counter Data
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AN ALTERNATIVE PERSPECTIVE ON THE WEIGHTED POINT MODEL FOR PASSIVE NEUTRON MULTIPLICITY COUNTING
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THE DESIGN OF A HIGH-EFFICIENCY NEUTRON COUNTER FOR WASTE DRUMS TO PROVIDE OPTIMIZED SENSITIVITY FOR PLUTONIUM ASSAY
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MOBILE HIGH EFFICIENCY MULTIPLICITY COUNTER FOR URANIUM MEASUREMENTS
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The Thick Target (α, n) Production Yield of Sulphur
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Nuclear Calibration of a Large Volume Calorimeter – 9318
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An Improved U-Pu System for Field Pu Measurements
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MOBILE INSTRUMENTATION FOR NUCLEAR MATERIAL CHARACTERIZATION
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TECHNICAL ISSUES AND ORGANIZATIONAL DEMANDS FOR COMBATING WMD PROLIFERATION
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