Scanuk: A collaborative programme to develop new zirconium cladding alloys
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
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References (30)
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18. The basic features of the isothermal promonotectoid transformation in a Zirconium 2.5% Nb alloy
19. Effect of neutron irradiation on the tensile properties of the zirconium 2.5% niobium alloy
20. The effect of heat treatment on the texture of fabricated zirconium-rich alloys
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24. Recent results on the out-of-pile corrosion of zirconium alloys at RML
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26. Nelson · CEAP-4089 · 1972 · Vol. II · 17.0
27. Corrosion of Zircaloy-2 fuel rod cladding in boiling water reactors
28. Zircaloy-clad UO2 fuel rod evaluation programme
29. Some observations of nodular corrosion of zircaloy cladding in a BWR environment
30. Oxidation and hydriding of Zircaloy in NPD Reactor