Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition

Shriwastaw, R. S.Sawarn, T. K.Banerjee, S.Rath, B. N.Dubey, J. S.Sunil KumarSingh, J. L.Bhasin, V.2018-01-102018-01-102017Journal of Nuclear Materials, 2017. Vol. 493: pp. 460-470http://hdl.handle.net/123456789/154344534 bytestext/htmlenLoss of coolant accidentSteam oxidationOxide layeralpha-Zr(O) layerCladding embrittlementRing tension testEstimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA conditionArticle