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Mohammad Alrwashdeh
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Proceedings Papers

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

Mohammad Alrwashdeh, Saeed A. Alameri
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16838
https://doi.org/10.1115/ICONE2020-16838
View Paper titled, Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors
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Topics: Fuels, Particulate matter, Very high temperature reactors, Coating processes, Coatings, Cycles, Graphite, High temperature, Monte Carlo methods, Nuclear fuel cycle
Journal Articles

U233 Data Evaluation for Criticality Study

Mohammad Alrwashdeh, Wang Kan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2016, 2(3): 034501.
Paper No: NERS-15-1118
https://doi.org/10.1115/1.4032814
Published Online: June 17, 2016
View Article titled, U233 Data Evaluation for Criticality Study
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Topics: Bayes methods, Computers, Cross section (Physics), Databases, Fittings, Thermal energy, Nuclear fission, Computer software, Neutrons
Proceedings Papers

233 U Evaluation Comparison Study

Mohammad Alrwashdeh, Aniseh Abdalla, Kan Wang
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30057
https://doi.org/10.1115/ICONE22-30057
View Paper titled, 233 U Evaluation Comparison Study
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Topics: Bayes methods, Computers, Cross section (Physics), Databases, Fittings, Resonance
Proceedings Papers

Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow

Aniseh A. A. Abdalla, Jiyang Yu, Mohammad Alrwashdeh
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A003, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30060
https://doi.org/10.1115/ICONE22-30060
View Paper titled, Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow
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Topics: Buoyancy, Flow (Dynamics), Turbulence, Accidents, Containment, Hydrogen, Nuclear power stations, Combustion, Explosions, Computation
Proceedings Papers

Nuclear Data Statistical Treatment

Mohammad Alrwashdeh, Jian Kai Yu, Aniseh Abdalla, Kan Wang
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A020, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16790
https://doi.org/10.1115/ICONE21-16790
View Paper titled, Nuclear Data Statistical Treatment
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Topics: Fittings