Search Results - "Samanta, Akanksha"
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Study of oxide and α-Zr(O) growth kinetics from high temperature steam oxidation of Zircaloy-4 cladding
Published in Journal of nuclear materials (01-12-2015)“…Oxidation kinetics of Zircaloy-4 cladding of fuel pins of Indian pressurized heavy water reactors (IPHWRs) under a simulated loss of coolant accident (LOCA)…”
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Influence of temperature and hydrogen content on the transverse mechanical properties of Zircaloy-4 fuel cladding
Published in Progress in nuclear energy (New series) (01-11-2022)“…This paper presents the results of the investigation on the influence of hydrogen on the transverse mechanical properties of the Zircaloy-4 fuel cladding at…”
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Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material
Published in Journal of nuclear materials (01-02-2021)“…•The effect of radial hydride on the room temperature fracture toughness of the Zr-2.5Nb pressure tube material was investigated.•The curved compact tension…”
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Probing structural evolution in thorium–cerium mixed oxides thermally annealed in oxidizing and reducing conditions
Published in Journal of nuclear materials (01-10-2020)“…ThO2 is a promising matrix either for incineration or direct disposal of plutonium and (Th, Pu)O2 is a potential advanced fuel. In this view, a ThO2–CeO2 mixed…”
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Experimental studies on hydrogen evolution from zirconium alloy based matrices using TGA-EGA
Published in Journal of radioanalytical and nuclear chemistry (01-10-2016)“…Main techniques used for measurement of Heq in zirconium based alloys (being used as major reactor components for PHWRs) are differential scanning calorimetry,…”
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