@article{sarkar_alsabbagh_murty_2014, title={Investigation of microstructure and mechanical properties of low dose neutron irradiated HT-9 steel}, volume={65}, ISSN={["0306-4549"]}, DOI={10.1016/j.anucene.2013.11.008}, abstractNote={HT-9 steel samples have been irradiated with fast neutrons (E > 0.1 MeV) to a low dose (1.2 × 10−3 dpa). Microstructure of the unirradiated and irradiated samples has been characterized by X-ray diffraction line profile analysis using different model-based approaches. The domain size and density of dislocations of the irradiated steel have been estimated. Different types of tensile tests have been carried out at room temperature to assess the changes in mechanical properties of HT-9 steel due to neutron irradiation.}, journal={ANNALS OF NUCLEAR ENERGY}, author={Sarkar, A. and Alsabbagh, A. H. and Murty, K. L.}, year={2014}, month={Mar}, pages={91–96} }
 @article{alsabbagh_sarkar_miller_burns_squires_porter_cole_murty_2014, title={Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel}, volume={615}, ISSN={["1873-4936"]}, DOI={10.1016/j.msea.2014.07.070}, abstractNote={Neutron irradiation effects on ultra-fine grain (UFG) low carbon steel prepared by equal channel angular pressing (ECAP) have been examined. Counterpart samples with conventional grain (CG) sizes have been irradiated alongside with the UFG ones for comparison. Samples were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to 1.37 dpa. Atom probe tomography revealed manganese and silicon-enriched clusters in both UFG and CG steel after neutron irradiation. Mechanical properties were characterized using microhardness and tensile tests, and irradiation of UFG carbon steel revealed minute radiation effects in contrast to the distinct radiation hardening and reduction of ductility in its CG counterpart. After irradiation, micro hardness indicated increases of around 9% for UFG versus 62% for CG steel. Similarly, tensile strength revealed increases of 8% and 94% respectively for UFG and CG steels while corresponding decreases in ductility were 56% versus 82%. X-ray quantitative analysis showed that dislocation density in CG increased after irradiation while no significant change was observed in UFG steel, revealing better radiation tolerance. Quantitative correlations between experimental results and modeling were demonstrated based on irradiation induced precipitate strengthening and dislocation forest hardening mechanisms.}, journal={MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING}, author={Alsabbagh, Ahmad and Sarkar, Apu and Miller, Brandon and Burns, Jatuporn and Squires, Leah and Porter, Douglas and Cole, James I. and Murty, K. L.}, year={2014}, month={Oct}, pages={128–138} }
 @article{alsabbagh_valiev_murty_2013, title={Influence of grain size on radiation effects in a low carbon steel}, volume={443}, ISSN={["1873-4820"]}, DOI={10.1016/j.jnucmat.2013.07.049}, abstractNote={Ultra-fine grain (UFG) metals with a relatively large volume of interfaces are expected to be more radiation resistant than conventional metals; grain boundaries act as unsaturable sinks for neutron irradiation induced defects. Effects of neutron irradiation on conventional and ultra-fine grain structured carbon steel are studied using the PULSTAR reactor at NC State University to relatively low fluence (∼1.15 × 10−3 dpa). The low dose irradiation of ultrafine grained carbon steel revealed minute radiation effects in contrast to the observed radiation hardening and reduction of ductility in its conventional grained counterpart.}, number={1-3}, journal={JOURNAL OF NUCLEAR MATERIALS}, author={Alsabbagh, Ahmad and Valiev, Ruslan Z. and Murty, K. L.}, year={2013}, month={Nov}, pages={302–310} }
 @inproceedings{sarkar_alsabbagh_murty, title={Effect of low dose neutron irradiation on tensile behavior of ht-9 steel at room temperature}, booktitle={TMS 2014 Supplemental Proceedings}, author={Sarkar, A. and Alsabbagh, A. H. and Murty, K. L.}, pages={147–154} }