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

  • 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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  • The Impact of Matrix Heterogeneity on Gamma-Ray Waste Assay
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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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