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模塊式高溫氣冷堆核電站

出版社:清華大學(xué)出版社出版時(shí)間:2020-05-01
開本: 16開 頁數(shù): 893
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模塊式高溫氣冷堆核電站 版權(quán)信息

模塊式高溫氣冷堆核電站 本書特色

本書為高溫氣冷堆核電站領(lǐng)域目前為止全球z具權(quán)威性、先進(jìn)性,甚至唯1的綜述性專著。 其主要內(nèi)容依托清華大學(xué)核研院牽頭組織的10兆瓦高溫堆實(shí)驗(yàn)堆的設(shè)計(jì)、研制與實(shí)施,此項(xiàng)目為國(guó)家重大科技專項(xiàng),國(guó)家863項(xiàng)目之一。 高溫氣冷堆具有良好的固有安全特性,是目前世界上比較先進(jìn)的商用反應(yīng)堆,在國(guó)家能源戰(zhàn)略中具有重要地位。中國(guó)的高溫氣冷堆技術(shù)研究及應(yīng)用,處于世界領(lǐng)x水平,對(duì)全球能源領(lǐng)域有多方面重要影響。 本書為讀者深入了解高溫氣冷堆的原理、技術(shù)發(fā)展?fàn)顩r、安全特性和潛在的應(yīng)用領(lǐng)域提供了詳盡闡述和充實(shí)資料 ,可為從事高溫氣冷堆技術(shù)領(lǐng)域工作的科研開發(fā)人員、項(xiàng)目管理人員以及政府官員全面了解高溫氣冷堆提供參考。

模塊式高溫氣冷堆核電站 內(nèi)容簡(jiǎn)介

  模塊式高溫氣冷堆是一種采用包覆顆粒燃料、以石墨為慢化劑、以氦氣為冷卻劑的反應(yīng)堆堆型。  高溫氣冷堆具有良好的固有安全特性,除可用于發(fā)電外,還可用于熱電聯(lián)供以及高溫工藝熱的應(yīng)用。高溫氣冷堆發(fā)電的余熱可采用空冷塔冷卻,因此可以建造在缺水地區(qū)!  赌K式高溫氣冷堆核電站(英文版)》為讀者深入了解高溫氣冷堆的原理、技術(shù)發(fā)展?fàn)顩r、安全特性和潛在的應(yīng)用領(lǐng)域提供了詳盡的闡述和充實(shí)的資料;可為從事高溫氣冷堆技術(shù)領(lǐng)域工作的科研開發(fā)人員、項(xiàng)目管理人員以及政府官員提供參考。

模塊式高溫氣冷堆核電站 目錄

1 General Aspects of High-Temperature Reactors
1.1 Overview
1.2 Future Sustainable Energy Technologies
1.3 Principle Characteristics of HTR
1.4 Application of Modular HTR in the Energy Economy
1.5 Safety Aspects of Modular HTR
1.6 Fuel Cycles of Modular HTR
1.7 Intermediate and Final Storage
1.8 Overview on the HTR-PM Project
1.9 Overview on the HTR Development up to Now
References

2 Physical Aspects of Core Layout
2.1 Overview on Physical Aspects of Core Layout and Design of Modular HTR Plants
2.2 Some Aspects of Criticality
2.3 Influence of Reflectors
2.4 Coefficients of Reactivity
2.4.1 Principle Consideration
2.4.2 Temperature Coefficients
2.5 Demand of Reactivity Compensation and Worth of Control Systems
2.6 Fast Neutron Doses on Reflectors
2.7 Influence of Flow of Balls,Action on the Burnup of Fuel
2.8 Distributions of Fuel,Neutron Flux,and Power Density in the Reactor Core
2.9 Principles of Kinetics of Nuclear Reactors
2.9.1 Overview on Some General Aspects
2.9.2 Kinetic Equations
2.9.3 Simple Solutions of the Kinetic Equations
2.10 Program Systems for Physical Layout of the Core
2.10.1 General Remarks
2.11 Aspects of Core Layout and Design
2.11.1 General Overview and Aspects of Core and Fuel Element Design
2.11.2 Discussions on Different Core Parameter
2.12 Physical Aspect of the First Loading and Running in Period of a Pebble Core
2.13 Discharging of Pebble-Bed Cores
References

3 Thermo-Hydraulic Aspects of Core Layout
3.1 Heat Production Inside the Core
3.2 Thermal Power of the Core
3.3 Data of the Coolant Gas Helium
3.4 Basic Equations of the Thermo-Hydraulics of the Core
3.5 Heating up of Helium Coolant in the Core
3.6 Temperature Profiles in Fuel Elements
3.7 Heat Transfer in the Pebble-Bed Core
3.8 Pressure Drops in the Core and Reflector Structures
3.9 Special Aspects of Thermo-Hydraulic Layout of the Core of Modular HTR
3.9.1 Mixing of Hot Gas Behind the Core
3.9.2 Influence of Bypasses on the Core Cooling
3.9.3 Uncertainties of Calculation of Power Density and Other Thermo-Hydraulic Parameters
3.9.4 Measurement of Fuel Temperature
3.9.5 y Heating of Core Internals and Cooling
3.10 Principle of Core Layout
3.11 Comparison of Data of Core Cooling in Some HTR Concepts
3.12 Comparison of Thermo-Hydraulic Aspects of Different Reactor Types
References

4 Fuel Elements
4.1 Description of the Component
4.2 Aspects of Layout and Design of HTR Fuel Elements
4.3 Temperature Distributions in HTR Fuel Elements
4.4 Irradiation Behavior of Fuel Elements
4.5 Stresses in Fuel Elements
4.6 Corrosion of Fuel Elements
4.7 Fission Product Release from Fuel Elements in Normal Operation
4.8 Different Types of Spherical Fuel Elements
4.9 Some Further Experiences with HTR Fuel Elements
4.10 Comparison of LWR and HTR Fuel Elements
References

5 Reactor Components
5.1 Overview on the Components
5.2 Internal Reactor Structures
5.2.1 Overview on the Components
5.2.2 Technical Aspects of Core Internals
5.2.3 Loads on Core Internals
5.2.4 Graphite and Its Irradiation Behavior
5.2.5 Results of Analysis of Reflector Structures During Operation
5.3 Primary Enclosure
5.3.1 Overview
5.3.2 Aspects of Dimensioning and Materials for Pressure Vessels of Primary Circuit
5.3.3 Neutron Irradiation of Reactor Pressure Vessel and Design Aspects
5.3.4 Activation of the Reactor Pressure Vessel
5.4 Comparison of Different Reactor Pressure Vessles
5.5 Shutdown and Control Systems
5.5.1 Overview on Reactivity Aspects
5.5.2 Worthes of Shutdown Systems in HTR
5.5.3 Technical Concepts of Control and Shutdown Systems
5.6 Fuel Handling System
……

6 Components of the Helium Cycle
7 Reactor Containment Building
8 Power Conversion Cycle
9 Operational Aspects
10 Safety Aspects and Analysis of Accidents
11 Fuel Cycles and Waste Management
12 Economic Aspects of Power Plants and Questions of Optimization
13 Development of HTR Technology
14 Some Experimental Results on Safety Aspects of Modular HTR
15 Future Aspects of HTR Development

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