PWR nuclear power plant operator personnel basic theory Training Series: nuclear reactor thermal hydraulics(Chinese Edition)

 
9787502247652: PWR nuclear power plant operator personnel basic theory Training Series: nuclear reactor thermal hydraulics(Chinese Edition)
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Paperback. Pub Date: December 2010 Pages: 213 Language: Chinese in Publisher: Atomic Energy Press PWR nuclear power plant operating personnel basic theory Training Series: nuclear reactor thermal hydraulics. mainly on the basic concepts of nuclear reactor thermal hydraulics The basic theory and some analysis and calculations. The book is divided into six chapters. including nuclear fuel cladding materials. coolant. and its thermal physical properties. heat release within the reactor. the reactor heat transfer. fuel elements. and heap the internal parts of the heat transfer and its temperature distribution. steady state conditions reactor fluid dynamics analysis. core steady-state thermal-hydraulic design. The basic theory of the pressurized water reactor nuclear power plant operator personnel Training Series: nuclear reactor thermal hydraulics is the basic theory of the pres...

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HAO LAO MI
ISBN 10: 7502247653 ISBN 13: 9787502247652
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liu xing
(JiangSu, JS, China)
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Book Description paperback. Condition: New. Ship out in 2 business day, And Fast shipping, Free Tracking number will be provided after the shipment.Pages Number: 213 Publisher: Atomic Energy Pub. Date :2010-12-01 version 1. HAO old fans compiled the nuclear reactor thermal hydraulics. mainly on nuclear reactor thermal hydraulics of the basic concepts. basic theory and some problems analysis and calculation. The book is divided into six chapters. including nuclear fuel. cladding materials. and thermal properties of the coolant. the heat release within the reactor. the reactor heat transfer. fuel elements and reactor internal components of the heat transfer and temperature distribution. the steady-state conditions reactor fluid dynamics analysis. steady-state reactor core thermal-hydraulic design. Nuclear reactor thermal hydraulics. is a pressurized water reactor nuclear power plant operators based theoretical training staff is one series of textbooks. but also for nuclear power engineering in the relevant technical staff and higher education teachers and students of nuclear engineering reference. Contents: Chapter 1. nuclear fuel. cladding materials. coolant and thermal properties of nuclear fuel 1.1 1.2 pairs of nuclear fuel. cladding materials and the general requirements of 1.2.1 coolant nuclear fuel cladding material 1.2.3 1.2.2 1.3 coolant nuclear fuel. cladding materials and coolant thermal properties 1.3.1 uranium dioxide fuel cladding thermal properties 1.3.2 and some structural materials. thermal properties of the major expansion coefficient 1.3.4 1.3.3 The thermal properties of water and water vapor convergence of 1.4 photos (or burn) the effects of thermal properties of irradiated 1.4.1 (or burn) the impact of the melting point of uranium dioxide irradiated 1.4.2 (or burn) the thermal conductivity of uranium dioxide effects 1.4.3 irradiation (or burnup) of the fuel pellet swelling of Review Questions Chapter 2 reactor heat release within the energy generated by nuclear fission 2.1 and 2.1.1 in the core distribution within the reactor core volume heat source 2.1.2 heat release rate 2.1.3 core and fuel elements of power within the core measure of representation 2.1.4 Distribution 2.1.5 The heat release rate of the factors that affect the core power distribution channel 2.2 nuclear heat (heat pipe) factor of 2.3 and reactor fuel rods Heat release 2.3.1 single-core fuel rods calculate the heat release 2.3.2 the calculation of total non-uniform heat release 2.4 core structural materials. moderator and pressure vessels. heat release 2.4.1 within the -core structural materials release 2.4.2 moderator thermal heat release 2.4.3 or thick-walled pressure vessels. heat release component of the 2.5 Ah after the shutdown cooling heat release and heat release 2.5.1 shutdown after power shutdown after 2.5.2 Review Questions Chapter 3 Cooling Heat Transfer 3.1 reactor heat transfer process inside the reactor fuel elements 3.1.1 3.1.2 cladding outer surface of the thermal conductivity and heat transfer between the coolant 3.1.3 coolant heat input within 3.2 solid 3.2.1 Thermal conductivity equation in Cartesian coordinates the heat conduction equation in cylindrical coordinate system 3.2.2 Heat Equation 3.3 single-phase convective heat transfer 3.3.1 viscous force. laminar and turbulent boundary layer velocity and temperature boundary layer 3.3.2 3.3 .3 velocity boundary layer thickness and the temperature boundary layer thickness and the heat transfer coefficient h of calculation 3.3.4 Single-phase forced convection heat transfer coefficient of natural convection heat transfer coefficient 3.3.5 3.4 3.4.1 Pool boiling heat transfer type boiling heat transfer flow boiling heat transfer 3.4.2 Review Questions Chapter 4 reactor fuel elements and the internal parts of the plate heat transfer and temperature distribution of 4.1 and thermal conductivity of the fuel element temperature distribution in its cross section for the exterior cladding and the coolant mass 4.1.1 the fuel hea. Seller Inventory # LH2547

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2.

HAO LAO MI
ISBN 10: 7502247653 ISBN 13: 9787502247652
New paperback Quantity Available: 1
Seller:
liu xing
(JiangSu, JS, China)
Rating
[?]

Book Description paperback. Condition: New. Paperback. Pub Date: December 2010 Pages: 213 Language: Chinese in Publisher: Atomic Energy Press PWR nuclear power plant operating personnel basic theory Training Series: nuclear reactor thermal hydraulics. mainly on the basic concepts of nuclear reactor thermal hydraulics The basic theory and some analysis and calculations. The book is divided into six chapters. including nuclear fuel cladding materials. coolant. and its thermal physical properties. heat release within the reactor. the reac. Seller Inventory # CC027396

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