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000778954 019__ $$a974650022$$a981776897
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000778954 0247_ $$a10.1007/978-981-10-2311-8$$2doi
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000778954 08204 $$a621.48$$223
000778954 1112_ $$aPacific Basin Nuclear Conference$$n(20th :$$d2016 :$$cBeijing, China)
000778954 24510 $$aProceedings of the 20th Pacific Basin Nuclear Conference.$$nVolume 1 /$$cHong Jiang, editor.
000778954 264_1 $$aSingapore :$$bSpringer,$$c2017.
000778954 300__ $$a1 online resource.
000778954 336__ $$atext$$btxt$$2rdacontent
000778954 337__ $$acomputer$$bc$$2rdamedia
000778954 338__ $$aonline resource$$bcr$$2rdacarrier
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000778954 5050_ $$aOrganising Committee; Contents; Power Reactor and New Buildings; 1 Analysis and Design of the Common Raft for a Chinese Third-Generation Nuclear Power Plant; Abstract; 1 Introduction; 2 Analysis and Design Process; 2.1 Finite Element Model; 2.1.1 Finite Element Model of Common Raft; 2.1.2 Models of Superstructures; 2.1.3 Finite Element Model of Foundation; 2.2 Stress Analysis and Reinforcement Calculation; 2.2.1 Load and Member Forces; 2.2.2 Reinforcement Calculation and Layout; 3 Stability Evaluation; 3.1 Safety Against Sliding; 3.2 Safety Against Overturning; 4 Conclusions; References
000778954 5058_ $$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 (t  greaterthan 100 °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
000778954 5058_ $$a2.9 Calculation of F Function3 Calculation Algorithms; 4 Application Example; 4.1 Initial Dimension of the TWC; 4.2 Stress Amplitudes and Cyclic Number; 4.3 Calculation Results and Analyses; 5 Conclusion and Prospection; References; 3 A Study on the Tensile Properties of Materials at Elevated Temperature in RCC-M; Abstract; 1 Introduction; 2 Technical Basis of Su and Sy in ASME BPVC; 3 Source of Su and Sy in RCC-M; 4 Analysis of the Verification Test at Elevated Temperature in RCC-M; 5 Conclusions; References; 4 Analysis Method of the Temperature for the Heavy Reflector; Abstract
000778954 5058_ $$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
000778954 5058_ $$a1 Introduction2 A Brief Introduction of Main Building of Conventional Island; 2.1 Main Building of Conventional Island Layout Scheme; 2.2 Material and Main Section; 2.3 Seismic Design Requirements and Natural Conditions; 2.4 Thermal Action; 2.5 Live Load; 3 Contrast Analysis of Structure Internal Force and Deformation of Frame Structure with Joint or not Under Earthquake; 3.1 Structural Vibration Period; 3.2 Floor Displacement; 3.3 The Amount of Material Analysis; 4 Calculation and Analysis of the Super-Long Frame Structure Under the Thermal Action
000778954 506__ $$aAccess limited to authorized users.
000778954 520__ $$aThis is the first in a series of three proceedings of the 20th Pacific Basin Nuclear Conference (PBNC). This volume covers the topics of Safety and Security, Public Acceptance and Nuclear Education, as well as Economics and Reducing Cost. As one in the most important and influential conference series of nuclear science and technology, the 20th PBNC was held in Beijing and the theme of this meeting was “Nuclear: Powering the Development of the Pacific Basin and the World”. It brought together outstanding nuclear scientist and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The book is not only a good summary of the new developments in the field, but also a useful guideline for the researchers, engineers and graduate students.
000778954 588__ $$aOnline resource; title from PDF title page (SpringerLink, viewed January 17, 2017).
000778954 650_0 $$aNuclear energy$$vCongresses.
000778954 650_0 $$aNuclear power plants$$vCongresses.
000778954 650_0 $$aNuclear industry$$vCongresses.
000778954 7001_ $$aJiang, Hong,$$eeditor.
000778954 77608 $$iPrint version:$$z9789811023101
000778954 852__ $$bebk
000778954 85640 $$3SpringerLink$$uhttps://univsouthin.idm.oclc.org/login?url=http://link.springer.com/10.1007/978-981-10-2311-8$$zOnline Access$$91397441.1
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