Understanding the Atom, Nuclear Reactors
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 60 |
Release | : 1964 |
Genre | : |
ISBN | : |
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Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 60 |
Release | : 1964 |
Genre | : |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 45 |
Release | : 1969 |
Genre | : |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 32 |
Release | : 1964 |
Genre | : |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 32 |
Release | : 1963 |
Genre | : Nuclear energy |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 52 |
Release | : 1966 |
Genre | : |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 56 |
Release | : 1971 |
Genre | : |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 24 |
Release | : 1964 |
Genre | : |
ISBN | : |
Author | : United States. Atomic Energy Commission |
Publisher | : |
Total Pages | : 46 |
Release | : 1969 |
Genre | : |
ISBN | : |
Author | : U.S. Atomic Energy Commission |
Publisher | : |
Total Pages | : 88 |
Release | : 1964 |
Genre | : Nuclear physics |
ISBN | : |
Author | : Amir Mesquita |
Publisher | : BoD – Books on Demand |
Total Pages | : 354 |
Release | : 2012-02-10 |
Genre | : Technology & Engineering |
ISBN | : 9535100181 |
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 and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in light-water reactors; methods for monitoring and controlling power in nuclear reactors; structural materials modeling for the next generation of nuclear reactors; application of the results of finite group theory in reactor physics; and the usability of vermiculite as a shield for nuclear reactor.