ISSN:
1573-8205
Source:
Springer Online Journal Archives 1860-2000
Topics:
Energy, Environment Protection, Nuclear Power Engineering
,
Physics
Notes:
Conclusions 1. On irradiating ZrH1.9 with an integrated flux of 3.2·1021 neutrons/cm2 (1.8·1020 neutrons/cm2 with energies over 1 MeV) at 50°C, zirconium vacancies accumulate, possibly together with small vacancy complexes (≤10 Å) and also defects in the hydrogen sublattice. The defects of the metallic sublattice cause swelling, an increase in hardness, and increased thermal and electrical resistance. The defects of the hydrogen sublattice increase the electrical resistance and reduce the lattice tetragonality. 2. The recovery of the properties on annealing the irradiated hydride at 50–540°C takes place in three stages; the first is associated with the migration of interstitial atoms, the second with vacancy migration, and the third with the annealing of complex defects. There are two temperature ranges of complex-formation: Close to 180°C aggregates of interstitial atoms are apparently formed, and at 270–450°C vacancy cavities (voids). 3. The recovery of the hydrogen sublattice takes place in the second and third stages. 4. The melting point of zirconium hydride (Tm=2155±75°K) may be estimated by comparing the annealing temperatures of similar defects in the hydride and fcc metals. The authors wish to thank V. I. Shcherbak for great help in the electron-microscope investigations.
Type of Medium:
Electronic Resource
URL:
http://dx.doi.org/10.1007/BF01134756
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