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Showing 1 to 6 of 6 for “"Alpha prime"”.
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X-Ray and Neutron Scattering Studies of Niobium-Hydrogen Alloys Near the Alpha-Prime to Beta Phase Transition
… alloys (0.70 < x < 0.85) in the vicinity of the (alpha)'-(beta) phase transition was conducted using x-ray and elastic neutron scattering techniques in the temperature range 300 < T < 473 K. Diffuse scattering close to the Bragg peaks of the BCC (alpha)' phase was measured. The temperature …
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An investigation into the influence of microstructural condition on the superelastic behaviour in Ti-Nb-based alloys.
… range of -196$^{\circ}$C to 30$^{\circ}$C. The $\alpha^{\prime\prime}$ martensite was observed to form when cold rolled material was cooled. In contrast, no evidence of the $\beta$ to $\alpha^{\prime\prime}$ transformation was observed in solution treated material, despite cooling to …
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Pharmacological inhibition of CK2: the effect of an FDA designated orphan drug on pathology, neuroinflammation, and glial phenotypes in Huntington’s disease
… in the pathophysiology of HD. Specifically, the alpha prime catalytic subunit of CK2 (CK2α’) is upregulated in HD, and genetic depletion of CK2α’ in HD mice results in improved motor behavior, decreased mutant Htt aggregation, and improved neuronal function. Silmitasertib (CX-4945) is an FDA …
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Radiation-induced microstructural and mechanical property modifications in advanced alloys
… alloy. The chromium content is close to the alpha–alpha prime phase boundary. Irradiation hardening in T91 is largely due to dislocation loops and network dislocations. The dislocation structure evolution was characterized by TEM during in situ 1 MeV Kr++ irradiation at 300, 400, and 500C. At …
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The microstructure and properties of hipped powder Ti alloys
… by simply tempering the (less deformed) original alpha prime martensite within the central part of original particles. Among the three HIPping temperatures used, samples machined from powder HIPped at 930°C exhibited a better balance of properties than those HIPped at 880°C or 1020°C. The fatigue …
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Irradiation damage in neutron-irradiated Fe-Cr model alloys
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generation IV fission reactors and future fusion reactors. Compared to austenitic stainless steels, these steels have superior properties in thermal conductivities and thermal expansion coefficients. In …