A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water
Stress Intensity Factor Solutions for Continuous Surface Flaws in Reactor Pressure Vessels
Implementing Corrosion-Fatigue Crack Growth Rate Data for Engineering Applications
Fracture Behavior of Stainless Steel
The Use of Fatigue Crack Growth Technology in Fracture Control Plans for Nuclear Components
Variable Flaw Shape Analysis for a Reactor Vessel Under Pressurized Thermal Shock Loading
Flaw Evaluation Handbook for Salem Units 1 and 2 Reactor Vessel Nozzle Safe and Weld Regions
Fracture Behavior of Stainless Steel
RV Closure Head Penetration
Equivalent Spring-mass System for Normal Modes
From an Indian Zenana
The Gold Coast Police, 1844-1938
A Modest Attempt to Prove Dr. H-- Not the Author of the Bouchain Dialogue. In a Letter to W. J. Now at the Bath. With a Catalogue of Choice Books Now in the Press