Technical Committees / Committee E10 / Committee Publications

Journal of Testing and Evaluation

• Loading Rate Effect on the Master Curve Reference Temperature, T₀, for the A533 B Material
• Simulation of Irradiation Effects in Reactor Pressure Vessel Steels: the Reactor for Virtual Experiments (REVE) Project
• A Study of the Variation of Neutron Skyshine Dose with Respect to Roof Thickness, Source Spectrum Distribution
• Development of a B4C/Al Cermet for Use as an Improved Structural Neutron Absorber
• Temperature Dependence of Dynamic Young's and Shear Moduli for Four Different Heat Treated Conditions of Depleted U-2Mo
• Prediction of the Shift in the Brittle-Ductile Transition Temperature of Light-Water Reactor (LWR) Pressure Vessel Materials
• An Assessment of Reactor Pressure Vessel Irradiated Materials Considerations
• Neutron Spectrum Analysis from Dosimetry Experiments
• Long-Term Dosimetry
• Damage Function Analysis
• Radiation Damage Units for Steel
• Dosimetry Related to Controlled Thermonuclear Research
• Structural Materials for Nuclear Power Plants