P. Rodriguez

TL;DR: In this paper, the authors present an assessment of the current understanding of the phenomenon of serrated plastic flow, which manifests itself as serrations, load drops, jerkiness or other discontinuities in the stress-strain curves obtained in constant extension rate tensile tests, and as sudden bursts of strain in constant loading rate tests and in constant load (stress) creep tests (the so called staircase creep).

TL;DR: In this article, the effect of microstructural changes, due to transformation of delta ferrite, on the associated variations that take place in the tensile and stress corrosion properties of type 316 L stainless steel weld deposits when subjected to postweld heat treatment at 873 K for prolonged periods (up to 2000 hours).

TL;DR: In this article, a nuclear grade AISI type 304 stainless steel in a boiling solution of 5M NaCl+ 0.15M Na2SO4+ 3 mL/L HC1 (bp 381 K) was presented.

TL;DR: In this article, a review of radiation effects in nuclear reactor materials has been made; the irradiation effects have been correlated with the crystal structure of the materials, and Metallurgical approaches for improving irradiation performance of materials and for developing new alloys with better resistance to radiation damage were pointed out.

TL;DR: In this article, the development of the indigenous plutonium-uranium mixed carbide nuclear fuel for the fast breeder test reactor was described, and the fuel has performed satisfactorily and produced, for the first time in our country, nuclear electricity from a fast reactor.