|Series||Monograph series on nuclear science and technology|
|Contributions||American Nuclear Society., U.S. Atomic Energy Commission. Division of Technical Information.|
|LC Classifications||TK9203.P7 C6 1980|
|The Physical Object|
|Pagination||xiii, 439 p. :|
|Number of Pages||439|
|LC Control Number||79057306|
This book is designed to assist the nuclear power plant operator by presenting the elements of the scientific and engineering disciplines supporting water technology of power reactors, and as an interpretive summary of the specialized literature in the field/5. Additional Physical Format: Online version: Cohen, P. (Paul). Water coolant technology of power reactors. New York, Gordon and Breach  (OCoLC) Get this from a library! Water coolant technology of power reactors. [P Cohen; American Nuclear Society.; U.S. Atomic Energy Commission. Division of Technical Information.]. This report is a survey of coolant technology in water cooled reactors which focuses on the following objectives: (a) man-sievert reduction; (b) plant life extension; (c) fuel life extension; (d) general safety and materials reliability. Contents: 1. Introduction; 2. Description of reactor coolant systems; 3.
The most common type of nuclear power plant uses water cooling within the reactor core. Water is a good moderator for the fast neutrons generated during nuclear fission and so easily combines the ability to slow the particles generated during fission reactions with the capture of heat. Two types of water-cooled reactor have been developed. Water as a reactor coolant. Water and steam are a common fluid used for heat exchange in the primary circuit (from surface of fuel rods to the coolant flow) and in the secondary circuit. It used due to its availability and high heat capacity, both for cooling and heating. It is especially effective to transport heat through vaporization and condensation of water because of its very large. A coolant in a nuclear reactor is a liquid or gaseous substance that passes through the reactor core and removes heat from the nuclear fission reaction.. In the double-circuit power reactors, the reactor coolant enters the steam generator, which produces steam that drives the turbines, and in the single-circuit reactors the coolant (steam or gas) can serve as the working fluid of the cycle of. The reactor coolant system of the pressurized water reactor (PWR) consists of a reactor vessel, steam generators, reactor coolant pumps, a pressurizer, and other elements. These principal components are interconnected by the reactor coolant piping to form a loop configuration.
A New Book: Light-Water Reactor Materials Authored by Donald R. Olander (corresponding author) of the Department of Nuclear Engineering at the University of California, Berkeley, and Arthur T. Motta of the Department of Mechanical and Nuclear Engineering at the Pennsylvania State University.. The contents of a new book currently in preparation are described. The technology developed for the Borax reactors was subsequently adopted by General Electric Co in the United States which developed a commercial nuclear reactor based on the boiling water concept. The first of these reactors, the Dresden Nuclear Power Plant in Illinois, USA, with a generating capacity of MW, began operating in and is. This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors. Boiling water reactors. Pressurized water reactors. Boiling water reactors; Pressurized water reactors; Notes "ANS-USAEC monograph." "Prepared under the direction of the American Nuclear Society for the Division of Technical Information, United States Atomic Energy Commission." Includes bibliographical references. commitment to retain