Pressurized Heavy Water Reactors: Candu Volume 7

ISBN-13: 9780128220542 / Angielski / Miękka / 2021 / 546 str.

Jovica Riznic

Spis treści

1. Introduction. World energy production and the contribution of PHWRs2. Nuclear fuel3. Zr<2.5Nb pressure tubes in CANDU4. Computational modeling of in-reactor deformation in CANDU fuel channels5. Design and aging management for feeder pipe and feeder supports6. Steam generators7. Electrical power systems8. Radiation protection9. Fitness for service and related concepts10. Fitness-for-service guidelines11. Feeders11. Overview of the Canadian Nuclear Safety Commission: Canada's nuclear regulator12. The extended operation and life extension project of Embalse Nuclear Power Plant: An account from a regulator's perspective13. Cernavoda: CANDU nuclear power plants in Romania14. Pressurized heavy water reactors probabilistic safety assessment15. Severe accident prevention and mitigation in pressurized heavy water reactors

O autorze

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.