Pressurized Heavy Water Reactors : Candu

Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs.

Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties.

• Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits
• Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina
• Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation

Jovica R Riznic, PhD., P.Eng., FASME, is a Technical Specialist with the Canadian Nuclear Safety Commission (CNSC), working on regulatory analysis and assessment of technical issues with operating nuclear power plants (NPP). He served CNSC on various position, including nuclear safety analysis and managing the CNSC Research and Support Program. He served as an adjunct professor/thesis advisor at the University of Waterloo, Mc Master, and Purdue Universities and currently is on faculty at Algonquin College in Ottawa in the School of Business and the Centre for Continuing and Online. He conducted research at Argonne National Laboratory, Purdue University and University of Wisconsin-Milwaukee in the areas of heat and mass transfer, nuclear reactor thermal hydraulics, multi-phase thermo-fluid systems, nuclear reactor safety and reliability, and engineering management. He is currently coordinating a team providing Canadian contribution to a number of international research projects with US Nuclear Regulatory Commission (NRC), Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD NEA) and International Atomic Energy Agency (IAEA) to address issues of material degradation and safe operation of piping components and steam generators of CANDU and Light Water Reactors. Also, he leads a team of researchers working with Purdue University on refining the CANTIA methodology for steam generator tube integrity, leakage inspection and probabilistic assessment. Currently he is the Founding Editor of the ASME Nuclear Engineering and Technology for 21st Century Concise Monographs Series, Associate Editor of the ASME Nuclear Engineering and Radiation Science Journal and the on the Editorial Board of the Nuclear Engineering and Design Journal.