Nuclear Engineering: Mathematical Modeling and Simulation - Tapa blanda

Acerca del autor

Zafar ullah Koreshi [B.Sc. (Hons) Nuclear Engineering, Queen Mary College, University of London (UK); M.S, Nuclear Engineering, University of Wisconsin, Madison (USA), Ph.D Nuclear Engineering, University of Cambridge] is Professor at Air University, having contributed as Dean Faculty of Engineering and currently is Dean Graduate Studies at Air University. His experience has been in the Pakistan Atomic Energy Commission, Dr. A Q Khan Research Laboratories, National University of Sciences and Technology, and at Air University, Islamabad. He has published in Annals of Nuclear Energy, Progress in Nuclear Energy, Nuclear Technology and Radiation Protection, ASME Journal of Nuclear Engineering and Radiation Sciences and at several other leading international journals. Dr. Koreshi has been Track Chair at the International Conference on Nuclear Engineering held in the USA, China and Japan and has presented his research at the American Nuclear Society Annual Meetings. He is Member American Society of Mechanical Engineers (ASME), Professional Engineer Pakistan Engineering Council and Life Member Pakistan Nuclear Society. He has also received commendations for being Reviewer of prestigious journals. Prof. Zafar Koreshi is an Associate Editor of the ASME Journal of Nuclear Engineering and Radiation Science.

De la contraportada

Nuclear Engineering Mathematical Modeling and Simulation presents the mathematical modeling of neutron diffusion and transport. Aimed at students and early career engineers, this highly practical and visual resource guides the reader through computer simulations using the Monte Carlo Method which can be applied to a variety of applications, including power generation, criticality assemblies, nuclear detection systems, and nuclear medicine to name a few. The book covers optimization in both the traditional deterministic framework of variational methods and the stochastic framework of Monte Carlo methods.

Specific sections cover the fundamentals of nuclear physics, computer codes used for neutron and photon radiation transport simulations, applications of analyses and simulations, optimization techniques for both fixed-source and multiplying systems, and various simulations in the medical area where radioisotopes are used in cancer treatment.