@article{computational evaluation on the use of some selected ceramic max-phase coatings as shielding layers on spent fuel dry cask canisters_2023, url={https://www.iosrjournals.org/iosr-jap/papers/Vol15-issue1/Ser-1/B1501010516.pdf}, journal={IOSR Journal of Applied Physics}, year={2023} }
 @article{alsmadi_bourham_2023, title={Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks}, volume={21}, ISSN={2214-9147}, url={http://dx.doi.org/10.1016/j.dt.2022.08.002}, DOI={10.1016/j.dt.2022.08.002}, abstractNote={The shielding and corrosion properties of the Alloy 709 advanced austenitic stainless steel have been investigated as a candidate canister material in spent fuel dry casks. The results revealed that the experimental and computational data of the linear and mass attenuation coefficients of the alloy are in good agreement, in which the attenuation coefficient values decreased with increasing photon energy. Alloy 709 was shown to exhibit the highest linear attenuation coefficient against gamma rays when compared to 304 and 316 stainless steels. On the other hand, Alloy 709 exhibited no considerable weight change over a 69-day period in circulating salt brines corrosion testing, while it showed an exponential increase of corrosion current density with temperature in acidic and basic corrosive solutions during electrochemical polarization corrosion testing. Furthermore, Alloy 709 was the least corroded steel compared to other austenitic stainless steels in both acidic and basic solutions. The optimistic results of the shielding and corrosion properties of Alloy 709 due to its chemical composition, suggest utilizing it as a canister material in spent nuclear fuel dry casks.}, journal={Defence Technology}, publisher={Elsevier BV}, author={Alsmadi, Zeinab Y. and Bourham, Mohamed A.}, year={2023}, month={Mar}, pages={116–124} }
 @article{alsmadi_bourham_2022, title={An assessment of protective coating dry cask canisters with structurally amorphous metals (SAMs) for enhanced radiation shielding}, volume={388}, ISSN={["1872-759X"]}, url={http://dx.doi.org/10.1016/j.nucengdes.2022.111647}, DOI={10.1016/j.nucengdes.2022.111647}, abstractNote={The shielding properties of the most common structurally amorphous metals (SAMs) as coating barriers for radiation shielding and corrosion have been computationally studied, for possible use on spent fuel dry cask canisters applications, using the Microshield computational simulation package. The results revealed that SAM1651 exhibited the highest attenuation coefficients and lowest exposure rates at low photon energies, which is attributed to its high elemental content of molybdenum (Mo) and yttrium (Y), while SAM2X5 exhibited the highest attenuation coefficients and lowest exposure rates at high photon energies, due to its high density (7.6 g/cm3) and its elemental content of manganese (Mn), tungsten (W) and silicon (Si). The third SAM material known as SAM 40 had the highest iron content (52.3%), but the results were close to the SAM2X5 as other components were similar, however, SAM2X5 was of higher density. The mean-free path (MFP) and half-value layer (HVL) were very similar for all the three tested SAM materials.}, journal={NUCLEAR ENGINEERING AND DESIGN}, publisher={Elsevier BV}, author={Alsmadi, Zeinab Y. and Bourham, Mohamed A.}, year={2022}, month={Mar} }
 @article{alsmadi_abouelella_alomari_murty_2022, title={Stress-Controlled Creep-Fatigue of an Advanced Austenitic Stainless Steel at Elevated Temperatures}, volume={15}, ISSN={["1996-1944"]}, url={https://www.mdpi.com/1996-1944/15/11/3984}, DOI={10.3390/ma15113984}, abstractNote={Creep–fatigue interaction occurs in many structural components of high-temperature systems operating under cyclic and steady-state service conditions, such as in nuclear power plants, aerospace, naval, and other industrial applications. Thus, understanding micromechanisms governing high-temperature creep–fatigue behavior is essential for safety and design considerations. In this work, stress-controlled creep–fatigue tests of advanced austenitic stainless steel (Alloy 709) were performed at a 400 MPa stress range and 750 °C with tensile hold times of 0, 60, 600, 1800, and 3600 s, followed by microstructural examinations. The creep–fatigue lifetime of the Alloy 709 was found to decrease with increasing hold time until reaching a saturation level where the number of cycles to failure did not exhibit a significant decrease. Softening behavior was observed at the beginning of the test, possibly due to the recovery of entangled dislocations and de-twining. In addition, hysteresis loops showed ratcheting behavior, although the mean stress was zero during creep–fatigue cycling, which was attributed to activity of partial dislocations. Microstructural examination of the fracture surfaces showed that fatigue failure dominated at small hold times where the cracks initiated at the surface of the sample. Larger creep cracks were found for longer hold times with a lower probability of dimpled cavities, indicating the dominance of creep deformation. The results were compared with other commonly used stainless steels, and plausible reasons for the observed responses were described.}, number={11}, journal={MATERIALS}, author={Alsmadi, Zeinab Y. and Abouelella, Hamdy and Alomari, Abdullah S. and Murty, K. L.}, year={2022}, month={Jun} }
 @article{alsmadi_murty_2021, title={Effect of Strain Range on High Temperature Creep-Fatigue Behaviour of Fe-25Ni-20Cr (wt.%) Austenitic Stainless Steel (Alloy 709)}, volume={38}, ISSN={["1878-6413"]}, url={https://doi.org/10.1080/09603409.2020.1859310}, DOI={10.1080/09603409.2020.1859310}, abstractNote={ABSTRACT Since the preliminary data suggest that Fe-25Ni-20Cr austenitic stainless steel (Alloy 709) is an excellent candidate as a structural material for high-temperature applications such as Sodium-cooled Fast Reactor (SFR), the effect of strain range on creep-fatigue interaction of the Alloy 709 is investigated by conducting strain-controlled creep-fatigue tests with tensile hold times of 0, 600, 1,800 and 3,600 s at strain ranges varying from 0.6% to 1.2% at 750°C and 2 × 10−3 s−1 strain rate. Strain-controlled fatigue tests were performed at strain ranges from 0.3% to 2.5% at 750°C and 2 × 10−3 s−1 strain rate. The predicted fatigue life of Alloy 709 shows a better correlation with the characteristic slopes predictive method. With increasing strain range at a given hold time, the number of failure cycles decreases until saturation. The fractography of the deformed samples exhibited increased number of cracks with strain range along with M23C6 precipitates and high dislocation density.}, number={1}, journal={MATERIALS AT HIGH TEMPERATURES}, publisher={Informa UK Limited}, author={Alsmadi, Zeinab Y. and Murty, K. L.}, year={2021}, month={Jan}, pages={47–60} }
 @article{enhanced shielding and mechanical properties of white cement mortars via celestobarite fine aggregate_2021, url={http://iaset.us/archives?jname=74_2&year=2021&submit=Search}, journal={International Journal of General Engineering and Technologyy}, year={2021} }
 @article{alsmadi_murty_2021, title={High-temperature effects on creep-fatigue interaction of the Alloy 709 austenitic stainless steel}, volume={143}, ISSN={["1879-3452"]}, url={https://doi.org/10.1016/j.ijfatigue.2020.105987}, DOI={10.1016/j.ijfatigue.2020.105987}, abstractNote={High-temperature creep-fatigue behavior of the Alloy 709 is investigated by performing strain-controlled creep-fatigue tests at 650 °C and 750 °C with tensile hold times of 0, 60, 600, 1,800 and 3,600 s at 1% strain range and strain rate of 2 × 10−3 s−1. Results revealed that creep-fatigue life at 650 °C fluctuates due to Dynamic Strain Aging (DSA) during hold periods. Linear damage summation (LDS) was employed to construct the creep-fatigue interaction diagram of the alloy at different loading conditions. An increased density of cracks and creep cavities is observed at 750 °C with less dislocation density compared to 650 °C.}, journal={INTERNATIONAL JOURNAL OF FATIGUE}, publisher={Elsevier BV}, author={Alsmadi, Zeinab Y. and Murty, K. L.}, year={2021}, month={Feb} }
 @article{shielding properties of 316 stainless steel with multi-layered barriers for spent fuel drycasks_2021, url={http://www.tjprc.org/publishpapers/2-44-1615371730-2IJPRJUN20212.pdf}, journal={International Journal of Physics and Research}, year={2021} }
 @article{alsmadi_alomari_kumar_murty_2020, title={Effect of hold time on high temperature creep-fatigue behavior of Fe-25Ni-20Cr (wt.%) austenitic stainless steel (Alloy 709)}, volume={771}, ISSN={["1873-4936"]}, DOI={10.1016/j.msea.2019.138591}, abstractNote={To understand high temperature creep-fatigue interaction of the Alloy 709, strain-controlled low-cycle fatigue (LCF) tests were performed at strain ranges varying from 0.3% to 1.2% with fully reversible cycle of triangular waveform at 750 °C. In addition, different hold times of 60, 600, 1800 and 3600 s were introduced at the maximum tensile strain to investigate the effect of creep damage on the fatigue-life at strain range of 1% at 750 °C. The creep-fatigue life and the number of cycles to macro-crack initiation and failure are found to decrease with increasing hold time indicating higher crack initiation and growth rates. Creep-fatigue life is evaluated by a linear summation of fractions of cyclic and creep damages according to ASME code. The fractographs of the samples deformed at 1% strain range indicated that fatigue might have been the dominant mode of deformation whereas, for the samples deformed at the same strain range with different hold times, both fatigue and creep have contributed to the overall deformation and fracture of the alloy.}, journal={MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING}, author={Alsmadi, Zeinab Y. and Alomari, Abdullah and Kumar, N. and Murty, K. L.}, year={2020}, month={Jan} }
 @article{shielding properties of alloy 709 advanced austenitic stainless steel as candidate canister material in spent fuel dry casks_2020, url={http://www.tjprc.org/publishpapers/2-44-1608272312-2IJPRDEC20202.pdf}, journal={International Journal of Physics and Research}, year={2020} }