Zeinab Alsmadi

From Waste to Shield: A Bibliometric Analysis (2004-2024) on Sustainable Radiation Protection Materials

Journal of Materials and Environmental Science. https://www.jmaterenvironsci.com/Document/vol17/vol17_N1/JMES-2026-1701010-Hamdi.pdf

Conceptual innovative designs of multi-layer spent nuclear fuel dry casks

ANS Student Conference. Presented at the ANS Student Conference, Albuquerque, NM.

Evaluation of shielding effectiveness of coated alloy 709 for nuclear spent fuel dry cask canisters

Annals of Nuclear Energy, 222, 111600.

Recycling of waste as radiation protection materials in the field of civil engineering

Days of Geology and Geotechnics. Presented at the Days of Geology and Geotechnics, Tunis Science City, Tunisia.

Computational evaluation on the use of some selected ceramic max-phase coatings as shielding layers on spent fuel dry cask canisters

IOSR Journal of Applied Physics. https://www.iosrjournals.org/iosr-jap/papers/Vol15-issue1/Ser-1/B1501010516.pdf

An assessment of protective coating dry cask canisters with structurally amorphous metals (SAMs) for enhanced radiation shielding

Nuclear Engineering and Design, 388, 111647.

Creep and creep-fatigue behavior of an advanced stainless steel (Alloy 709) – application to sodium-cooled fast reactors

International Conference on Fast Reactors and Related Fuel Cycles (FR22). Presented at the International Conference on Fast Reactors and Related Fuel Cycles (FR22), Vienna, Austria.

On coating spent nuclear fuel dry cask canisters with structurally amorphous metals (SAMs

2nd International Virtual Conference on Materials Science and Engineering. Presented at the 2nd International Virtual Conference on Materials Science and Engineering.

Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks

Defence Technology, 21, 116–124.

Stress-Controlled Creep–Fatigue of an Advanced Austenitic Stainless Steel at Elevated Temperatures

Materials, 15(11), 3984.

Enhanced shielding and mechanical properties of white cement mortars via celestobarite fine aggregate

International Journal of General Engineering and Technologyy. http://iaset.us/archives?jname=74_2&year=2021&submit=Search

Shielding properties of 316 stainless steel with multi-layered barriers for spent fuel drycasks

International Journal of Physics and Research. https://scholar.google.com/scholar?hl=en&as_sdt=0%2C5&q=SHIELDING+PROPERTIES+OF+316+STAINLESS+STEEL+WITH+MULTI-LAYERED++BARRIERS+FOR+SPENT+FUEL+DRYCASKS&btnG=

Creep-fatigue interaction of an advanced austenitic stainless steel (Alloy 709)

Global 2019 International Nuclear Fuel Cycle Conference and Top Fuel 2019 Light Water Reactor Fuel Performance Conference, 743–747. https://www.scopus.com/inward/record.url?eid=2-s2.0-85081090064&partnerID=MN8TOARS

Effect of Strain Range on High Temperature Creep-Fatigue Behaviour of Fe-25Ni-20Cr (wt.%) Austenitic Stainless Steel (Alloy 709)

Materials at High Temperatures, 38(1), 47–60.

High-temperature effects on creep-fatigue interaction of the Alloy 709 austenitic stainless steel

International Journal of Fatigue, 143, 105987.

Shielding properties of alloy 709 advanced austenitic stainless steel as candidate canister material in spent fuel dry casks

International Journal of Physics and Research. https://scholar.google.com/scholar?hl=en&as_sdt=0%2C5&q=SHIELDING+PROPERTIES+OF+ALLOY+709+ADVANCED+AUSTENITIC+STAINLESS+STEEL+AS+CANDIDATE+CANISTER+MATERIAL+IN+SPENT+FUEL+DRY+CASKS&btnG=

Creep-Fatigue Deformation of an Advanced Austenitic Stainless Steel (Alloy 709)

Alomari, A., Alsmadi, Z., Kumar, N., & Murty, K. (2019, January 1). Transactions of the American Nuclear Society - Volume 121, Vol. 121, pp. 187–191.

Effect of hold time on high temperature creep-fatigue behavior of Fe–25Ni–20Cr (wt.%) austenitic stainless steel (Alloy 709)

Materials Science and Engineering: A, 771, 138591.

High Temperature Low-Cycle Fatigue and Creep-Fatigue Behavior of Fe-25Ni-20Cr Austenitic Stainless Steel

Alsmadi, Z., Alomari, A. S., Kumar, N., & Murty, K. L. (2019, December 5). River Publishers EBooks, pp. 155–162.

High temperature cyclic deformation behavior of an advanced austenitic stainless steel (Alloy 709)

19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors Envdeg 2019, 1069–1075. https://www.scopus.com/inward/record.url?eid=2-s2.0-85080050973&partnerID=MN8TOARS