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Nuclear Reactor Technology Development and Utilization. Woodhead Publishing Series in Energy

  • ID: 4894790
  • Book
  • June 2020
  • Region: Global
  • 250 Pages
  • Elsevier Science and Technology
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Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear setting. As countries across the globe realize their plans for a sustainable energy future, the need for innovative nuclear reactor design is increasing, and this book will provide a deep understanding of how these technologies can aid in a region's goal for clean and reliable energy.

Dr Khan and Dr Nakhabov, alongside their team of expert contributors, discuss a variety of important topics, including nuclear fuel cycles, plant decommissioning and hybrid energy systems, while considering a variety of diverse uses such as nuclear desalination, hydrogen generation and radioisotope production. Knowledge acquired enables the reader to conduct further research in academia and industry, and apply the latest design, development, integration, safety and economic guidance to their work and research.

  • Combines reactor fundamentals with a contemporary look at evolving trends in the design of advanced reactors and their application to both nuclear and non-nuclear uses
  • Analyses the latest research and uses of hybrid systems which bring together nuclear technology with renewable energy technologies
  • Presents applications, economic factors and an analysis of sustainability factors in one comprehensive resource
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Introduction to Nuclear Technology Yuri A. Kazansky 1. Fundamentals of nuclear reactors Saeed A. Alameri 2. Nuclear fuel cycle and decommissioning Bahman Zohuri and Bahman Zohuri 3. Nuclear reactor safety Dmitrii S. Samokhin 4. Economics of nuclear power Giorgio Locatelli 5. Small Modular reactors (SMRs) Marco Enrico Ricotti and Roman V. Fomin 6. Generation IV nuclear reactors Bahman Zohuri 7. Nuclear Desalination Youssef Shatilla 8. Nuclear Hydrogen Georgy Levanovich Khorasanov 9. Engineering materials in advanced space applications Liviu Popa-Simil 10. Research reactors and non-power applications of nuclear energy Alla A. Udalova 11. Nuclear hybrid energy system Bahman Zohuri 12. Nuclear Power Plant Development Jamal Khaer Ibrahim 13. Nuclear powered space reactor Velidi V S S Gurunadh
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Khan, Salah Ud-Din
Dr. Salah Ud-Din Khan is Assistant Professor at Sustainable Energy Technologies Center, King Saud University, Saudi Arabia. He researches in the field of nuclear reactor safety while conducting work on NK/TH coupling and in reactor core design. His work contained in designing and simulation of reactor technology is well proven and published in highly reputed journals. He also modified simulation codes to be employed in nuclear reactor analysis, and his areas of research include desalination, cost estimation concept, probabilistic safety assessment, radiological protection, nuclear forensics, radiation-shielding materials, computational techniques for synthesizes and development of materials. He managed projects on small modular nuclear reactors, material development and on desalination systems. He is on the editorial board of American Association for Science and Technology (AASCT), USA and acts as a guest editor for journals. His tenure of experience ranges from Lecturer, Senior Researcher, Assistant Professor, and Visiting Scientist/Professor in reputed institutes and universities. He has published around 100 international research articles with accumulative impact factor of 110. He has authored three books and contributed to many other book publications.
Nakhabov, Alexander V.
Dr. Alexander Nakhabov is currently working as Associate Professor at Obninsk Institute for Nuclear Power Engineering of the National Research Nuclear University MEPhI. He is a supervisor of educational programs ("Electronics and automation of physical installations” and "Nuclear power engineering and thermal physics”) in Nuclear Physics and Engineering Department and Head of department of international education and collaboration. From 2013 - 2016 he was the Dean of the Physics and Power Engineering faculty, where higher education of Russian and foreign students (from Vietnam, Turkey, Mongolia and Jordan) in nuclear power engineering field was concentrated. His professional interests are in methods and automated systems for non-destructive testing of nuclear power plants' (NPPs) materials and pipelines; technical diagnostic systems for NPPs including algorithms of diagnosis, hardware and software; methods and algorithms for data processing and analysis including artificial intelligence and data mining methods. From 2007 - 2008 he participated in in-service welding joints inspection for equipment and pipelines of Tianwan NPP (Units 1 and 2, China) as analyst in automated ultrasonic testing group (NIKIMT-Atomstroy, Russia). From 2009 - 2012 Dr. Nakhabov took on the position of first rank engineer at Chief Designer Department of Scientific Research Institute of Nuclear Instrumentation (JSC "SNIIP", Moscow). He is the developer of systems for automated analysis of ultrasonic and radiographic testing results applying NPP welding joints (in cooperation with Engineering Diagnostics Center of NIKIET, Moscow). He provides lectures on Nuclear Pear Engineering and Applications at various universities in Russia and oversees.
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