A creep limit approach to the design of Zircaloy-2 reactor pressure tubes at 275 °C
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
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References (7)
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1. Watkins · ASTM, STP 458 · 1969
2. Private communication from A. Perry (Winfrith, England).
3. Irradiation effects in Zirconium alloy pressure tubes
4. Hesketh · J. Nucl. Mater. · 1968 · 26 · 7710.1016/0022-3115(68)90159-1 ↗
5. B. T. Kelly and S. N. Buckley, private communication.
6. Radiation Damage in Solids and Reactor Materials
7. Lee · Trans. Met. Soc. AIME · 1967 · 239 · 103