On Predicting the Deformations and Stress Concentrations Associated with the Circumferential Ridging of Nuclear Reactor Fuel Cladding
High temperature tensile testing of fuel cladding, phase I : the primary and secondary creep properties for as-received zircaloy cladding in the temperature range of 900 [deg]C to 1200 [deg]C
High temperature tensile testing of fuel cladding. phase i : the primary and secondary Creep properties for as-received zircaloy cladding in the temperature range of 900 degrees c to 1200 degrees c
Development and generic design requirements for a pressure tube rolled joint made using a chromium-plated end fitting
Assessment and management of ageing of major nuclear power plant components important to safety : CANDU pressure tubes
Technical Memorandum CWTM-18W1320-03 : Stresses in a Pickering Endplate Due to In-plane Gravity Loading
On predicting the expansion of zircaloy nuclear reactor fuel cladding being rapidly heated to high temperatures
Technical Memorandum CWTM-18W1320-05 : Prediction of the Creep Sag Rate for Horizontal Fuel Elements While at High Temperature
A discussion about the use of the concept of internal stress in modelling the high temperature deformation of zircaloy