2014 Semi-Annual Progress Letter Report on Used Nuclear Fuel Integrity Study in Transportation Environments

A New Approach for Bimaterial Interface Fracture Toughness Evaluation

A New Approach for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

A New Approach to Determine the Quasi-Static and Dynamic Fracture Toughness of Engineering Materials

A New Approach to Evaluate Fracture Toughness of Structural Materials

article by J. A. Wang & K. C. Liu published 2004 in Journal of Pressure Vessel Technology

A New Approach to Evaluate Fracture Toughness of Structural Materials

scholarly article published 2003

A New Method for Dynamic Fracture Toughness Determination Using Torsion Hopkinson Pressure Bar

A New Test Method for Determining the Strength and Fracture Toughness of Cement Mortar and Concrete

A new technique for the prediction of non-linear material behavior

AN INNOVATIVE TECHNIQUE FOR THIN FILM INTERFACE TOUGHNESS RESEARCH

An Innovative Technique for Bi-Material Interface Toughness Research

An Innovative Technique for Evaluating the Integrity and Durability of Wind Turbine Blade Composites

An Innovative Technique for Evaluating the Integrity and Durability of Wind Turbine Blade Composites - Final Project Report

scientific article

BWR Spent Nuclear Fuel Interfacial Bonding Efficiency Study

scientific article

CIRFT Data Update and Data Analyses for Spent Nuclear Fuel Vibration Reliability Study

article

CIRFT testing of high-burnup used nuclear fuel rods from pressurized water reactor and boiling water reactor environments

Corrigendum to “The development of in situ fracture toughness evaluation techniques in hydrogen environment” [Int J Hydrogen Energy 40 (2015) 2013–2024]

article

Determination of Interfacial Fracture Toughness for Thin Film Coating Materials

article published in 2005

Developing Fatigue Pre-crack Procedure to Evaluate Fracture Toughness of Pipeline Steels Using Spiral Notch Torsion Test

article

Developing an Innovative Field Expedient Fracture Toughness Testing Protocol for Concrete Materials

Development of In Situ Techniques for Torsion and Tension Testing in Hydrogen Environment

Development of a Pulsed Pressure-Based Technique for Cavitation Damage Study

article

Development of spiral notch torsion test

article

Effect of Pressure on Plastic Collapse Under the Combined Bending and Torsion Moments for Circumferentially Surface Flawed Pipes

Effective Lifetime Estimate of Crimped Powerline Splice Connector Operated at High Temperature

article published in 2008

Effects of gamma-induced displacements on HFIR pressure vessel materials

Evaluating Stress-Corrosion Cracking Susceptibility Using a Torsion Test

article

FY 2014 Status Report: Quantification of CIRFT System Biases and Uncertainties Associated When Testing High Burnup Spent Nuclear Fuel

article

FY14 Status Report: CIRFT Testing Results on High Burnup UNF

FY15 Status Report: CIRFT Testing of Spent Nuclear Fuel Rods from Boiler Water Reactor Limerick

scientific article

INVESTIGATION OF PIPELINES INTEGRITY ASSOCIATED WITH PUMP MODULES VIBRATION FOR PUMPING STATION 9 OF ALYESKA PIPELINE SERVICE COMPANY

article

Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels

Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

Integrity Study of ACSR and ACSS Two Stage Splice Connectors at High Operation Temperatures

scientific article published on 9 November 2012

Interface fracture toughness evaluation for MA956 oxide film

Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database

Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels

Manufacturing Cost Analysis of Novel Steel/Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen

scholarly article published 1 September 2012

Measurement of Fracture Toughness of Materials With Non-Uniform Microstructure Based on Spiral Notch Torsion Test

Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications

scientific article

Methodology for Mechanical Property Testing on Fuel Cladding Using an Expanded Plug Wedge Test

Neutron Residual Stress Mapping for Spent Nuclear Fuel Storage Canister Weldment

Oak Ridge National Laboratory (ORNL) Spiral Notch Torsion Test (SNTT) System

PR-EDB: Power Reactor Embrittlement Database - Version 3

Potential Impact of Interfacial Bonding Efficiency on Used Nuclear Fuel Vibration Integrity During Normal Transportation

Progress Letter Report on Bending Fatigue Test System Development for Spent Nuclear Fuel Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.4)

article

Progress Report on Reverse Bending Fatigue Testing of Zry-4 Surrogate Rod

article

Residual Stress Evaluation within a Crimped Splice Connector Assembly

Reversible Bending Fatigue Testing System Design Concepts for Spent Fuel Vibration Integrity Study

Smart patch integration development of compression connector structural health monitoring in overhead transmission lines

Spiral Notch Torsion Test Use for Determining Fracture Toughness of Structural Materials

The Development of Expansion Plug Wedge Test for Clad Tubing Structure Mechanical Property Evaluation

article

The Development of Radiation Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels

article

The Development of Reversible Bending Fatigue Tester and Its Application to High Burnup Spent Nuclear Fuel Vibration Integrity Investigation under Normal Transportation

article

The Impact of Interface Bonding Efficiency on High Burn-up Spent Fuel Vibration Integrity during Normal Transportation

article

The Integrity of ACSR Full Tension Single-Stage Splice Connector at Higher Operation Temperature

The Integrity of ACSR Full Tension Splice Connector at Higher Operation Temperature

The Integrity of ACSR Full Tension Splice Connector at Higher Operation Temperature

The Lifetime Estimate for ACSR Single-Stage Splice Connector Operating at Higher Temperatures

scientific article

Using Finite Model Analysis and Out of Hot Cell Surrogate Rod Testing to Analyze High Burnup Used Nuclear Fuel Mechanical Properties

Using Torsion Bar Testing to Determine Fracture Toughness of Ceramic Materials

Using portable/in-situ stress-strain microprobe system to measure mechanical properties of steel bridges during service