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|a UAMI
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|a Brennen, Christopher E.
|q (Christopher Earls),
|d 1941-
|e author.
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1 |
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|a Thermo-hydraulics of nuclear reactors /
|c Christopher Earls Brennen, California Institute of Technology Pasadena, California.
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|a New York, NY :
|b Cambridge University Press,
|c [2016]
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|c ©2014
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|a 1 online resource
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|a Includes bibliographical references and index.
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0 |
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|a Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents.
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|a "This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation"--
|c Provided by publisher
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|a Print version record.
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|a English.
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|a Knovel
|b ACADEMIC - Electrical & Power Engineering
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|a Nuclear reactors
|x Fluid dynamics.
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|a Nuclear energy.
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|a Nuclear Energy
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|a Énergie nucléaire.
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7 |
|a nuclear power.
|2 aat
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|
7 |
|a Nuclear energy.
|2 fast
|0 (OCoLC)fst01039951
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|
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|a Nuclear reactors
|x Fluid dynamics.
|2 fast
|0 (OCoLC)fst01040800
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776 |
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8 |
|i Print version:
|a Brennen, Christopher E. (Christopher Earls), 1941-
|t Thermo-hydraulics of nuclear reactors.
|d New York, NY : Cambridge University Press, [2016]
|z 9781107139602
|w (DLC) 2015039287
|w (OCoLC)924626171
|
856 |
4 |
0 |
|u https://appknovel.uam.elogim.com/kn/resources/kpTHNR0003/toc
|z Texto completo
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