Experimental and numerical investigation on thermo-mechanical behavior of fuel rod under simulated LOCA conditions
Authors:
- Ashwini Kumar YadavAYAshwini Kumar Yadav
- Chang Hwan ShinCSChang Hwan Shin
- Sung Uk LeeSLSung Uk Lee
- Hyo Chan KimHKHyo Chan Kim
- 1 October 2018
- journal article
- research article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 337, 51-65
Abstract
No abstract availableKeywords
This publication has 15 references indexed in Scilit:
- Behavior of High Burn-up Fuel Cladding under LOCA ConditionsJournal of Nuclear Science and Technology, 2009
- Deformation of zircaloy-4 cladding during a LOCA transient up to 1200 CNuclear Engineering and Design, 2004
- Experimental determination of creep properties of Zirconium alloys together with phase transformationScripta Materialia, 2004
- Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review1987
- The oxidation behavior of Zircaloy‐4 in steam between 600 and 1600°CMaterials and Corrosion, 1985
- A model to predict the failure of zircaloy-4 fuel sheathing during postulated loca conditionsJournal of Nuclear Materials, 1984
- Lwr fuel rod behavior during reactor tests under loss-of-coolant conditions: results of the FR2 in-pile testsJournal of Nuclear Materials, 1982
- Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident1982
- Zirconium Cladding Deformation in a Steam Environment with Transient Heating1979
- Thermal accommodation coefficients of inert gases on stainless steel and UO2Journal of Nuclear Materials, 1974