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000781225 0247_ $$a10.1007/978-981-10-2314-9$$2doi
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000781225 1112_ $$aPacific Basin Nuclear Conference$$n(20th :$$d2016 :$$cBeijing, China)
000781225 24510 $$aProceedings of the 20th Pacific Basin Nuclear Conference.$$nVolume 3 /$$cHong Jiang, editor.
000781225 264_1 $$aSingapore :$$bSpringer,$$c2017.
000781225 300__ $$a1 online resource
000781225 336__ $$atext$$btxt$$2rdacontent
000781225 337__ $$acomputer$$bc$$2rdamedia
000781225 338__ $$aonline resource$$bcr$$2rdacarrier
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000781225 500__ $$aInternational conference proceedings.
000781225 5050_ $$aOrganising Committee; Contents; Power Reactor and New Buildings; 1 Analysis and Design of the Common Raft for a Chinese Third-Generation Nuclear Power Plant; Abstract; 1 Introduction; 2 Analysis and Design Process; 2.1 Finite Element Model; 2.1.1 Finite Element Model of Common Raft; 2.1.2 Models of Superstructures; 2.1.3 Finite Element Model of Foundation; 2.2 Stress Analysis and Reinforcement Calculation; 2.2.1 Load and Member Forces; 2.2.2 Reinforcement Calculation and Layout; 3 Stability Evaluation; 3.1 Safety Against Sliding; 3.2 Safety Against Overturning; 4 Conclusions; References.
000781225 5058_ $$a2 A Fatigue-Crack Propagation Analysis Program and Its ApplicationAbstract; 1 Introduction; 2 Theoretical Models; 2.1 Symbol Table; 2.2 Law of the Fatigue-Crack Propagation; 2.3 FCGR of the Austenite Stainless Steel Within Primary Coolant Environment of PWR Plant; 2.4 FCGR of the Austenite Stainless Steel Within Primary Coolant Environment of BWR Plant; 2.5 FCGR of the Steel in the Air (tss greaterthan 100ss°C); 2.6 Calculation of the Crack-Opening Half Length; 2.7 Calculation of the Variation Range of the Stress Intensity Factor; 2.8 Calculation of the Variation Range of the Stress.
000781225 5058_ $$a2.9 Calculation of F Function3 Calculation Algorithms; 4 Application Example; 4.1 Initial Dimension of the TWC; 4.2 Stress Amplitudes and Cyclic Number; 4.3 Calculation Results and Analyses; 5 Conclusion and Prospection; References; 3 A Study on the Tensile Properties of Materials at Elevated Temperature in RCC-M; Abstract; 1 Introduction; 2 Technical Basis of Su and Sy in ASME BPVC; 3 Source of Su and Sy in RCC-M; 4 Analysis of the Verification Test at Elevated Temperature in RCC-M; 5 Conclusions; References; 4 Analysis Method of the Temperature for the Heavy Reflector; Abstract.
000781225 5058_ $$a1 Introduction2 Analysis Method and Calculation Modal; 2.1 Analysis Method; 2.2 Calculation Modal; 2.2.1 Mesh Modal; 2.2.2 Mesh Sensitivity Analysis; 2.3 Boundary and Load Conditions; 2.3.1 Boundary Conditions; 2.3.2 Load; 3 Results Analysis and Evaluation; 3.1 Calculation Results; 3.2 Factors Affecting Temperature Field; 3.2.1 Influence of Loading Method; 3.2.2 Influence of Loading Conditions; 3.2.3 Influence of Material Properties; 3.2.4 Influence of Initial Temperature; 4 Conclusions; References; 5 Analysis on Super-Long Frame Structure of Main Building of Conventional Island; Abstract.
000781225 5058_ $$a1 Introduction2 A Brief Introduction of Main Building of Conventional Island; 2.1 Main Building of Conventional Island Layout Scheme; 2.2 Material and Main Section; 2.3 Seismic Design Requirements and Natural Conditions; 2.4 Thermal Action; 2.5 Live Load; 3 Contrast Analysis of Structure Internal Force and Deformation of Frame Structure with Joint or not Under Earthquake; 3.1 Structural Vibration Period; 3.2 Floor Displacement; 3.3 The Amount of Material Analysis; 4 Calculation and Analysis of the Super-Long Frame Structure Under the Thermal Action.
000781225 506__ $$aAccess limited to authorized users.
000781225 520__ $$aThis is the third in a series of three proceedings of the 20th Pacific Basin Nuclear Conference (PBNC). This volume covers the topics of Power Reactor and New Buildings, Waste Management, Acquiring Medical and Biological Benefits and Student program. As one in the most important and influential conference series of nuclear science and technology, the 20th PBNC was held in Beijing and the theme of this meeting was “Nuclear: Powering the Development of the Pacific Basin and the World”. It brought together outstanding nuclear scientist and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The book serves as a useful reference not only for the professionals and public to know more about nuclear industry, but also for policymakers to adjust or make energy strategies.
000781225 588__ $$aOnline resource; title from PDF title page (SpringerLink, viewed February 22, 2017).
000781225 650_0 $$aNuclear energy$$vCongresses.
000781225 650_0 $$aNuclear power plants$$vCongresses.
000781225 650_0 $$aNuclear industry$$vCongresses.
000781225 7001_ $$aJiang, Hong,$$eeditor.
000781225 77608 $$iPrint version:$$z9811023131$$z9789811023132$$w(OCoLC)953599042
000781225 85280 $$bebk$$hSpringerLink
000781225 85640 $$3SpringerLink$$uhttps://univsouthin.idm.oclc.org/login?url=http://link.springer.com/10.1007/978-981-10-2314-9$$zOnline Access$$91397441.1
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