Determination of internal stresses in bruce unit 2 rolled joints by axial profile measurements
Mechanical properties of zircaloy-2 : an evaluation for hanford n-reactor pressure tubes
Beta heat treated zircaloy
Irradiation growth of hafnium
Summary of experimental information relating to Creep and growth of calandria tubes
Verification of a model for in-reactor Creep transients in zirconium
High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K
Proposal to measure the temperature dependence and anisotropy of uniaxial Creep of pressure tube materials
The examination of components removed from pickering ngs unit 1 fuel channels g04, g14, g16, g20, k05, k18, and p14
The effect of cold-work and stress-relieving on the irradiation growth behaviour of zirconium alloys
Design basis for Creep of zirconium alloy components in a fast neutron flux
The effect of neutron fluence on the Creep and growth of annealed zircaloy-4 at 340 k
Proposal for low temperature stress relaxation and irradiation growth experiments in NRX reactor
Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation
Uniaxial In-Reactor Creep of Zirconium Alloys
Factors affecting in-core dimensional stability of zircaloy-2 calandria tubes
High-Temperature Irradiation Growth in Zircaloy
In-reactor Creep Machines
Influence of Neutron Irradiation on Tensile Properties of the Zirconium-2.5 Weight Per Cent Niobium Alloy
The fabrication and evaluation of five 5 percent cold-worked and two annealed excel pressure tubes