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Thermal Hydraulic Fundamentals, Second Edition, 2nd Edition

Description This book covers the basics behind thermal hydraulics. It explores the characteristics of power reactors, thermal design principles, and how reactors generate heat. The text also presents transport equations for single- and two-phase flows.

The authors discuss the thermodynamics of nuclear energy conversion systems, including nuclear power plants and a simplified power system. They also consider the thermal analysis of fuel, single-phase fluid mechanics and heat transfer, and two-phase flow dynamics and heat transfer. The final chapter presents a steady-state analysis of a single heated channel. A solutions manual is available for qualifying instructors.

Nuclear Systems Volume I : Thermal Hydraulic Fundamentals

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Stock photo. Kazimi Neil E. Search Results Results 1 of Todreas; Mujid S. Very Good. Disclaimer:A copy that has been read, but remains in excellent condition.

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Pages are intact and are not marred by notes or highlighting, but may contain a neat previous owner name. The spine remains undamaged. Dust jacket quality is not guaranteed. Todreas; Mujid S Kazimi.

Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition

CRC Press. Used book in good condition. Has wear to the cover and pages. Compared with single-phase heat transfer, heat transfer with a phase change is an effective way of heat transfer.

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It generally has high value of heat transfer coefficient due to the large value of latent heat of phase change followed by induced mixing of the flow. Boiling and condensation heat transfers are concerned with wide range of phenomena. Pool boiling is boiling at a stagnant fluid. Its behavior is well characterized by Nukiyama boiling curve , [3] which shows the relation between the amount of surface superheat and applied heat flux on the surface.

Nuclear Systems Volume I Thermal Hydraulic Fundamentals

With the varying degrees of the superheat, the curve is composed of natural convection, onset of nucleate boiling, nucleate boiling , critical heat flux , transition boiling, and film boiling. Each regime has a different mechanism of heat transfer and has different correlation for heat transfer coefficient. Flow boiling is boiling at a flowing fluid. Compared with pool boiling, flow boiling heat transfer depends on many factors including flow pressure, mass flow rate, type of fluid, upstream condition, wall materials, geometry of the system, and applied heat flux.

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Characterization of the flow boiling requires comprehensive consideration of operating condition. Heat transfer coefficient due to nucleate boiling increases with wall superheat until they reach a certain point.

Todreas & Kazimi, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition, 2e

When the applied heat flux exceeds the certain limit, heat transfer capability of the flow decreases or significantly drops. The reduced heat transfer coefficient seen in post-DNB or post-dryout is likely to result in damaging of the boiling surface.

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Understanding of the exact point and triggering mechanism related to critical heat flux is a topic of interest. For DNB type of boiling crisis, the flow is characterized by creeping vapor fluid between liquid and the wall. On top of the convective heat transfer, radiation heat transfer contributes to the heat transfer.