Technical Papers

IPAN / PANDDA

-Operational Experience with an Imaging Passive/Active Neutron System (IPAN) in a Mature Production Application to Perform WIPP Certified Non-Destructive Assays

-Non-Destructive Assay of Transuranic (TRU) Rad-Waste Sludges Using the Imaging Passive Active Neutron (IPAN) Technique

-Qualification of Boxed Waste Non-Destructive Assay Systems for Materials Control and Accountability Measurements at RFETS

-Multi-Purpose Crate Counter for the RFETS

-IPAN/GEA Active Neutron Assay: Finding the Plutonium Lump

-Performance of WIPP Certifiable Mobile Waste Characterization NDA Measurements on TRU waste Drums at LLNL

-IPAN/GEA Efficiency-Times-Attenuation Method for Waste Characterization

-Measurement Results for the IPAN/GEA Boxed Waste Assay System

-Greatly Improved Transuranic Waste Assay Accuracy Using Neutron Signal Imaging

-High Sensitivity Imaging Passive and Active Neutron (IPAN) Transuranic Assay System

-Imaging Boxed Waste Assay System

SuperHENC

-Innovations in the Assay of Un-Segregated Multi-Isotopic Grade TRU Waste Boxes with SuperHENC and FRAM Technology

-WIPP Certification of a New SuperHENC at Hanford for Assay of Transuranic Waste in Standard Waste Boxes

-Operational and Regulatory Performance of Waste Crate Assay Systems at RFETS

-SuperHENC: Final Performance and Certification Summary

-Performance Assessment of the Add–A–Source Matrix Correction Method Using the Super High Efficiency Neutron Coincidence Counting System (SuperHENC)

Spent Fuel

-Spent Fuel Measurements in Support of Burnup Credit

-Operational Experience in Radiometric Instrumentation for Spent Fuel Monitoring

-Spent Fuel Characterisation for Burnup Credit, Safeguards and Waste Disposal Applications

-Radiometric Instrumentation for Burnup Credit, Safeguards and Waste Characterization of Spent Fuel

-Modular Stand Alone Spent Fuel Monitoring Systems Bring Significant Cost Savings in Storage, Transport and Disposal

-Radiometric Instrumentation for Spent Fuel Monitoring

-High Sensitivity Neutron Assay of Grouted Spent Nuclear Fuel Sludge at Hanford

-In-situ Underwater Characterization of Radioactive Sludge

Reprocessing

-Improved Assay of Highly Active Reprocessing Waste by the Use of a Linear Accelerator Based Neutron Source

-Spent Fuel and Residue Measurement Instrumentation at the Sellafield Nuclear Fuel Reprocessing Facility

-NDA Systems Used by EURATOM at the THORP Feed Pond

-Development and Application of Special Instrumentation for Materials Accountancy and Process Control in Spent Fuel Recycle Plants

-Provision of NDA Instrumentation for the Control of Operations on Plutonium Finishing and Waste Plants at the Sellafield Nuclear Fuel Reprocessing Facility

-Multipurpose In-line Special Instrumentation in Spent Fuel Recycle Plants

-Advanced Non-Destructive Assay Systems and Special Instrument Requirements for Recycling Facilities

Remote Handled

-High Sensitivity Assay of Cement Encapsulated Spent Nuclear Fuel Sludge Using the Imaging Passive Active Neutron (IPAN) System

-Application of the PAN/GEA/AK method to the Non-Destructive Assay of Remote Handled TRU Waste

-Meaningful Characterisation of High Beta Gamma Radwaste by Radiometric Instrumentation

-Difficult But Not Impossible: Monitoring Highly Active Wastes Retrieved From Interim Storage Facilities

-Waste Crate Assay System: Assay Solutions for Very Large Remote Handled Crates

Miscellaneous

-Application of Spectral Summing to Suspect Low Level Debris Drums at Los Alamos National Laboratory

-Fast Enrichment Screening for ‘Go/No Go’ Classification of Large Containers

-Performance Comparison of Different Active Neutron Interrogation Techniques for Safeguards Applications

-Assay of Uranium Contaminated Waste in Intermodal Containers by Passive Neutron Measurement at the Oak Ridge 3 Building D&D Project

-Applications of the TRU-D Portable Package Monitor for Rapid Gram Estimation of Plutonium Bearing Waste Packages at the Point of Origin

-Accessing the Inaccessible: an Innovative Approach to the Radiological Surveying of Metal Waste

-Non-Destructive Measurement Uncertainty at a Plutonium Scrap Recovery Facility

-Recent Developments in Active Neutron Interrogation of 235u by Combined Transmission and Emission Measurements

-A 3-Dimensional Method for In-Situ Characterization of Buried Transuranic Waste using a Large Area Neutron Monitor

-Characterization of the Process Mechanical Cell at West Valley

-Radiation Tolerance Assessment of CIDAS

-Enhanced Spatial and Spectroscopic Resolution for First Responders

-Application of Remote Gamma Imaging Surveys at the Turkey Point PWR Reactor Facility

-Use of Gamma Ray Imaging Instruments in Support of TRU Waste Characterization Challenges

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