Ahmad Alsabbagh
- Name
- Dr Ahmad Alsabbagh
- Institution
- Jordan University of Science and Technology
- Position
- Assistant Professor
- h-Index
- ORCID
- 0000-0001-9059-5025
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"Influence of grain size on radiation effects in a low carbon steel."
Ahmad Alsabbagh, Ruslan Valiev, Korukonda Murty,
Journal of Nuclear Materials
Vol. 443
2013
302-310
Link
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. |
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"Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel"
Ahmad Alsabbagh, Apu Sarkar, Brandon Miller, Jatuporn Burns, Leah Squires, Douglas Porter, James Cole, Korukonda Murty,
Materials Science and Engineering A
Vol. 615
2014
128-138
Link
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. |
Neutron Irradiation Effects on Microstructure Properties of Ultra-Fine Grained Steel - FY 2014 RTE 2nd Call, #482
Post Irradiation Examination of ATR-irradiated ECAP'ed Steel. - FY 2013 RTE Solicitation, #405
Post Irradiation Examination of ATR-irradiated Nanocrystalline Materials - FY 2012 RTE Solicitation, #332
Post Irradiation Examination of ATR-irradiated Ultra-Fine Grained Steel - FY 2014 RTE 1st Call, #450
Effects of neutron irradiation on mechanical properties of nanocrystalline metals - FY 2014 RTE 1st Call, #462
Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel - FY 2018 RTE 1st Call, #1151
Fission Gas Behavior and Fuel Swelling of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation - FY 2017 RTE 2nd Call, #957
In Situ Observation of Lunar Crater Features in Xe Irradiated UO2 at High Dose - FY 2016 RTE 2nd Call, #657
Investigation of gas bubble behavior in metals using in-situ Ne, Ar and Kr ion irradiation - FY 2018 RTE 1st Call, #1213
The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels - FY 2017 RTE 3rd Call, #1105
About Us
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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