Stress Relaxation in Zircaloy-2 During Irradiation at Less Than 100°C
Author | : J. Walter Joseph |
Publisher | : |
Total Pages | : 28 |
Release | : 1961 |
Genre | : Stress relaxation (Physics) |
ISBN | : |
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Author | : J. Walter Joseph |
Publisher | : |
Total Pages | : 28 |
Release | : 1961 |
Genre | : Stress relaxation (Physics) |
ISBN | : |
Author | : Battelle Memorial Institute. Radiation Effects Information Center |
Publisher | : |
Total Pages | : 266 |
Release | : 1967 |
Genre | : |
ISBN | : |
Author | : J. Baicry |
Publisher | : |
Total Pages | : 19 |
Release | : 1987 |
Genre | : Anisotropy |
ISBN | : |
Irradiation tests conducted for the Advanced Fuel Assembly (AFA) grid development allowed the measurement of the mechanical characteristics, growth, and relaxation of the following materials: stress-relieved, ?-annealed, and ?-quenched Zircaloy-4, and ?-annealed Zr-3Sn-1Mo. The mechanical characteristics of the zirconium alloys approached a limit value as early as 5 x 1024 n m-2, except for the ?-quenched Zircaloy-4 for which the limit value was reached later at about 5 x 1025 n m-2. Uniform elongation at 588 K showed a minimum at about 5 x 1024 n m-2; beyond this fluence, stress-relieved Zircaloy-4 presented the most marked tendency to increase. Longitudinal direction growth of annealed Zircaloy-4 and longitudinal and transverse direction growth of stress-relieved Zircaloy-4 may be expressed by the formula ? = A(?t)n where n = 0.67 (stress-relieved Zircaloy-4) and n = 0.4 (annealed Zircaloy-4). It is doubtful that the growth is associated with a density change. The stress-relaxation of the zirconium base materials is nearly complete for 4 x 1025 n m-2, with the exception of Zr-1Nb which has an intermediate behavior between those of Zircaloy-4 and Inconel 718.
Author | : Radiation Effects Information Center (Columbus, Ohio). |
Publisher | : |
Total Pages | : 46 |
Release | : 1968 |
Genre | : Radiation |
ISBN | : |