Science And Technology Of Liquid Metal Coolants In Nuclear Engineering

Science and Technology of Liquid Metal Coolants in Nuclear Engineering is a comprehensive consolidation of the latest research and knowledge on liquid metal coolants. Over the last decades, various new technologies have been developed for the liquid metal coolants of fast breeder and fusion reactors and accelerator driven systems. Details of pumps and instrumentation used in these coolants and their operating principles are included to provide the reader with a well-rounded understanding of the topic and to guide on the operation of different liquid metal coolant systems. Methods for the safe handling and control of impurity levels in these coolants are clearly discussed, along with alkali metal fires and their management, including methods for safe disposal of sodium waste. Discusses the thermophysical and chemical properties of liquid metals described with their microscopic origin Includes methods for the safe handling of liquid metal coolants and their purification and management Discusses pumps and instrumentation principles and design

This publication provides a comprehensive summary of the status of liquid coolant technology development for fast reactors with regard to basic data, main technological challenges and the various fast reactor concepts and designs that are being investigated, with a special emphasis on the choice of coolant. The chapters are divided as follows: (1) Introduction; (2) Short History of Nuclear Power Development; (3) Physical and Chemical Properties of Coolants (Sodium, Lead and Lead-Bismuth Alloy); (4) Comparison of Different Sodium and Lead Coolant Technologies; (5) Thermohydraulics of Reactor Core; (6) Coolant Radioactivity; (7) Liquid Metal Cooled Fast Reactor Technology Development; (8) Modular Lead-Bismuth Cooled Small Size Fast Reactors; (9) Liquid Lead Cooled Fast Reactors

Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications

This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.

The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. Thus, one desires a coolant which possess a low cross section for absorbing neutrons, good heat-transfer efficiency, a low melting point and a high boiling point. The element gallium possesses some of the requisite properties. It is a unique material, having a very low melting point, and a very high boiling point. Being a liquid metal, the heat transfer characteristics would be good, though not so good as those of some other liquid metals. The absorption cross section of gallium is rather high, which is a severe handicap. Since the cross section might be reduced by proper alloying, and since good coolants need be present in the reactor in only relatively small amounts, one cannot rule out the use of gallium on account of its cross section alone. Since gallium had some promise as a reactor coolant, research on the subject was merited.

The present report intends to provide comprehensive and detailed information on LMFR technology. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors, on the following topics: experience in construction and operation, reactor physics and safety, sore structural material and fuel technology, fast reactor engineering and activities in progress on LMFR plants.

This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).