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Zafar Ullah Koreshi
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Proceedings Papers

Design and Non-Proliferation Viability of Small Modular Reactors

Zafar ullah Koreshi
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81651
https://doi.org/10.1115/ICONE26-81651
View Paper titled, Design and Non-Proliferation Viability of Small Modular Reactors
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Topics: Design, Small modular reactors, Nuclear power, Carbon, Emissions, Nuclear reactors, Power density, Risk, Safety, Signals
Journal Articles

Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

Zafar Ullah Koreshi, Hamda Khan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031018.
Paper No: NERS-15-1021
https://doi.org/10.1115/1.4032702
Published Online: June 17, 2016
View Article titled, Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm
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Topics: Explosives, Genetic algorithms, Neutrons, Optimization, Diffusion (Physics), Water, Design, Signals, Sensors
Proceedings Papers

Stationarity Issues in Monte Carlo Simulation for Neutron Transport

Zafar Ullah Koreshi
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, V005T11A001, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15016
https://doi.org/10.1115/ICONE21-15016
View Paper titled, Stationarity Issues in Monte Carlo Simulation for Neutron Transport
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Topics: Neutrons, Simulation, Cycles, Diffusion (Physics), Entropy, Signal processing, Signals
Proceedings Papers

Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion

Zafar Ullah Koreshi, Sadaf Siddiq
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 251-258, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29971
https://doi.org/10.1115/ICONE18-29971
View Paper titled, Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion
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Topics: Diffusion (Physics), Neutrons, Simulation, Slabs, Electromagnetic scattering, Geometry, Radiation scattering, Scattering (Physics), Aluminum, Eigenfunctions
Proceedings Papers

Vibration Analysis of a Multispan Tube in a Bundle

Shahab Khushnood, Zaffar M. Khan, M. Afzaal Malik, Zafar Ullah Koreshi, Mehmood Anwer Khan
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 563-572, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22210
https://doi.org/10.1115/ICONE10-22210
View Paper titled, Vibration Analysis of a Multispan Tube in a Bundle
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Topics: Computers, Damping, Design, Failure, Flow (Dynamics), Heat exchangers, Pipes, Process industries, Turbulence, Vibration
Proceedings Papers

Steady MHD Flow for Molten Metal Coolants in Advanced Nuclear Systems

Zafar Ullah Koreshi
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 579-581, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49567
https://doi.org/10.1115/ICONE12-49567
View Paper titled, Steady MHD Flow for Molten Metal Coolants in Advanced Nuclear Systems
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Topics: Coolants, Flow (Dynamics), Magnetohydrodynamics, Metals, Magnetic fields, Pressure drop, Computer simulation, Engineering design, Fluids, Lithium