Advanced Reactor Concepts (ARC)

Nuclear engineers advancing the energy transition are understanding more about the next generation of nuclear plants; however, it is still difficult to access all the critical types, concepts, and applications in one location. Advanced Reactor Concepts (ARC): A New Nuclear Power Plant Perspective Producing Energy gives engineers and nuclear engineering researchers the comprehensive tools to get up to date on the latest technology supporting generation IV nuclear plant systems. After providing a brief history of this area, alternative technology is discussed such as electromagnetic pumps, heat pipes as control devices, Nuclear Air-Brayton Combined Cycles integration, and instrumentation helping nuclear plants to provide dispatchable electricity to the grid and heat to industry. Packed with examples of all the types, benefits, and challenges involved, Advanced Reactor Concepts (ARC) delivers the go-to reference that engineers need to advance safe nuclear energy as a low-carbon option. - Describes theory and concepts on generation IV technology such as advanced reactor concepts (ARC) and electromagnetic pumps, and compares different types and sizes. - Sets out the energy transition with critical carbon-free technology that can supplement intermittent power sources such as wind and solar. - Explains alternative heat storage technology, including Nuclear Air-Brayton Combined Cycles. - Introduces advanced main instrumentation systems for in-core probes.

Ali Zamani Paydar is currently a nuclear engineer researcher and mechanical engineer, studying advanced reactor technology from the perspective of deploying emerging advanced nuclear reactor concepts. Ali earned a bachelor's degree in atomic physics from the University of Tehran and earned his master's degree in nuclear engineering from Amirkabir University of Technology (Tehran Polytechnic). After graduation, he pursued his career as a nuclear researcher and mechanical engineer, specifically in the field of thermal hydraulics and heat transfer of Pressurized Water Reactors (PWR). His main areas of focus are computational fluid dynamics and thermal hydraulics of nuclear reactors from a safety perspective in situations such as boiling, flow instability, and critical heat flux in generation IV nuclear reactors and strategic plans for the proper development of this technology in human life. He has published several papers and books on nuclear technology.