Influence of final recrystallization heat treatment on Zircaloy-4 strip corrosion-Reference-Cited by-同舟云学术

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Influence of final recrystallization heat treatment on Zircaloy-4 strip corrosion

Published:1990-09 Issue:2 Volume:173 Page:164-178
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Foster John P.,Dougherty J.,Burke M.G.,Bates J.F.,Worcester S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference10 articles.

1. Zirconium in the Nuclear Industry, American Society for Testing and Materials;Johnson;ASTM-STP 633,1977

2. Zirconium in the Nuclear Industry;Rudling,1987

3. Zirconium in the Nuclear Industry;Wadman,1988

4. Zirconium in the Nuclear Industry;Charquet,1988

5. Zirconium in the Nuclear Industry;Charquet,1987

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1. Improvement and prediction technology of the water-side corrosion of zirconium alloy: the developmental tendency;Journal of Physics: Conference Series;2024-08-01

2. The rolling schedule of Zircaloy-4 strip during multi-schedule and multi-pass hot rolling process;The International Journal of Advanced Manufacturing Technology;2023-11-29

3. Prediction and analysis of temperature distribution, during the multi-pass hot rolling of nuclear power zirconium alloy under different rolling schedules;The International Journal of Advanced Manufacturing Technology;2022-04-01

4. Twinning behaviors and grain refinement mechanisms during friction stir processing of Zr alloy;Materials Characterization;2020-05

5. Small-angle neutron scattering measurements of δ-phase deuteride (hydride) precipitates in Zircaloy 4;Journal of Applied Crystallography;2018-05-09

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