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Case Study
Zirconium Oxide Thickness Measurement Using FTIR
Case Study
TSS (Terminal Solid Solubility) Tool
Case Study
Treating and Processing Radioactive Liquid Legacy Waste
Case Study
TRUSTIE UpGrades
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Stator Bar Failure Analysis
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Spent Ion Exchange Resins - Retrieval and Packaging for a Waste…
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Safety Analysis Report - Nuclear Waste Management
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Seismic Qualification of 10 inch Butterfly Valve
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Reverse Engineering of a Dual Redundant Switching Power Supply
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SorbWebTM Plus Secondary Oil Containment System
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Reverse Engineering of an Analog Panel Meter
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Reverse Engineering of a Current Output Station Module
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Refurbishment & Maintenance to Avoid Obsolescence of the…
Case Study
Reference Scaling Factors for Low and Intermediate Level Waste
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Resin Sampling and Analysis
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Replica Examination of Nuclear Generating Station’s Bleed…
Case Study
Refurbishment and Support for Two CANDU Heat Exchangers
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Recovery and Over-packing of Carbon Steel Resin Liners for a…
Case Study
Reactor Safety Criticality Coding for Multi-Unit CANDU NPP
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Radionuclide Inventory | In-Service and Out-of-Service Nuclear…
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Radiation Shielding
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Radiochemical Characterizations - Lab Support
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Radiation Protection Engineering Support Services Project
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Qualification of Grout
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Qualification of Actuators - IEEE 382
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Prototype Nuclear Inspection Tool Analysis with CFX®
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Performance of Reinforced Concrete Structures Subjected to…
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Preliminary Decommissioning Plan for a Nuclear Station in Europe
Case Study
PRA Methodology for Seismic Events and Fire Hazards
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Nuclear Parts and Services
Case Study
Non-Nuclear Class Registration of 42 Inch Butterfly Valves
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Mixed Liquid Waste - Processing and Disposal
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Modified 37 Fuel Bundle Design Qualification
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Large Volume Dedication and Assembly
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Low and Medium Voltage Cable Qualification
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Instant Release Fractions for Failed Fuel Stored in Deep…
Case Study
Hot Particle Removal Project I Removal of the Hottest Fugitive…
Case Study
Fuels and Materials Cells Safety Analysis Report
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Identification of a Radioactive Contaminated Polymer
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Fuel Design Support for the Advanced CANDU Reactor
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In-Cabinet Seismic Response Spectra
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Forensic Examination of Rubber Expansion Joint
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Forensic Examination of Leaking Rubber Hose
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Fish Diversion System Barrier Net
Case Study
Examination of Fiberglass Reinforced Plastic Components in a…
Case Study
Fatigue Testing of Steam Generator Materials
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Forensic Analysis of CANDU Fueling Machine Clutch Plate
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Effects of Compressed Air on Ice Plugs: Testing on Feeder…
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Conditional Release Pathways Analysis
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Decommissioning Waste Disposal Options
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Commmercial Grade Dedication for Outage Support
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Disposal of Low and Intermediate Level Waste: A Techno-Economic…
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Direct Replacement Assemblies for Discontinued Equipment
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Compressor Testing and Qualification
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Cernavoda Tritium Removal Facility
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Battery Storage Program
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Assessment of Stored Nuclear Waste Containers
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Building Endstate Strategy Project - PNGS
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Cable Flame Testing
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A Strategy for Fuel Bundle Deformation - CANDU Owners Group