1-17 of 17 Books

Zirconium in the Nuclear Industry
By Craig M. Eucken
Role of internal stresses in the transient of irradiation growth of Zircaloy-2
Role of internal stresses in the transient of irradiation growth of Zircaloy-2
By Atomic Energy of Canada Limited.

Effects of anisotropy and irradiation on the creep behavior of zircaloy-2
By Glenn E. Lucas
The effect of neutron irradiation and cold work on the strain ageing behaviour of Zircaloy-2
The effect of neutron irradiation and cold work on the strain ageing behaviour of Zircaloy-2
By K. Veevers
Zirconium in the nuclear industry
Zirconium in the nuclear industry
By International Conference on Zirconium in the Nuclear Industry Stratford-upon-Avon 1978.
Tem examination of irradiated Zircaloy - 2 pressure tube material
Tem examination of irradiated Zircaloy - 2 pressure tube material
By D. Srivastava
The metallurgical examination of a cold-worked zircaloy-2 pressure tube irradiated in the U-2 loop
The metallurgical examination of a cold-worked zircaloy-2 pressure tube irradiated in the U-2 loop
By W. J. Langford
Metallurgical properties of cold-worked zircaloy-2 pressure tubes irradiated for five years in the NPD reactor
Metallurgical properties of cold-worked zircaloy-2 pressure tubes irradiated for five years in the NPD reactor
By W. J. Langford
The solid solubility of Ni and Co in [alpha]-Zr
The solid solubility of Ni and Co in [alpha]-Zr
By

Zirconium in the nuclear industry
By R. B. Adamson,Leo F. P. Van Swam
Formation and stability of Fe-rich precipitates in dilute Zr(Fe) single-crystal alloys
Formation and stability of Fe-rich precipitates in dilute Zr(Fe) single-crystal alloys
By
Estimation of fracture toughness and critical crack length of zircaloy pressure tube from ring tension test
Estimation of fracture toughness and critical crack length of zircaloy pressure tube from ring tension test
By Bhabha Atomic Research Centre
Zirconium in the nuclear industry
Zirconium in the nuclear industry
By
Tensile properties of irradiated calandria tubes at low to high rates of strain
Tensile properties of irradiated calandria tubes at low to high rates of strain
By
Tensile properties of Zr-2.5Nb pressure tube alloy between 25 and 800 ̊C
Tensile properties of Zr-2.5Nb pressure tube alloy between 25 and 800 ̊C
By R. N. Singh
Delayed hydride cracking velocity and crack growth measurement using DCPD technique in Zr-2.5Nb pressure tube material
Delayed hydride cracking velocity and crack growth measurement using DCPD technique in Zr-2.5Nb pressure tube material
By R. N. Singh
Delayed hydride cracking velocity and crak growth measurement using DCPD technique in Zr-2.5Nb pressure tube material
Delayed hydride cracking velocity and crak growth measurement using DCPD technique in Zr-2.5Nb pressure tube material
By R. N. Singh