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Proceedings of The 20th Pacific Basin Nuclear Conference

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Table of Contents

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    Book Overview
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    Chapter 1 A Study of AP1000 Nuclear Power Plant SGTR Event Processing Strategy
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    Chapter 2 A Summary of the Guidelines on the Evaluation of V&V Tools for Safety Digital I&C Software in Nuclear Power Plant Systems
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    Chapter 3 Analysis and Handling of Turbine Eccentricity Anomaly
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    Chapter 4 Analysis and Summarization of Continuous Spray Test on Pressurizer of Fuqing Nuclear Power Plant Unit 1
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    Chapter 5 Analysis of the CRDM Coils Current Interference and the Abnormal Display of Rod Position in RGL System
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    Chapter 6 Application of Key Interlock in HUALONG-I 3rd Nuclear Unit
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    Chapter 7 Charpy Impact Properties of Electron Beam Welded V-4Cr-4Ti Alloy
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    Chapter 8 Conclusion of the Test of Fujian Fuqing Nuclear Power Plant Unit 1 Determination of Reactor Coolant Flow on the Basis of the Heat Balance
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    Chapter 9 Exceptional Shut Down During Load Test of Emergency Diesel Generator
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    Chapter 10 Fangjiashan Auxiliary Transformer Low-Voltage Side of Three-Phase Voltage Imbalance Analysis
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    Chapter 11 Design for High Level Layout and Control of Nuclear Island HVAC Based on DCS Technique
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    Chapter 12 Improvements to CANDU6 Reactor Power Control Programs
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    Chapter 13 Main Control Room Design of Advanced Nuclear Reactor
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    Chapter 14 Material Substitute Research of the Main Pipeline Bracket Protection Cushion in CPR1000 NPP
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    Chapter 15 Nuclear Steam Generator Water Level Control Based on DFNN
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    Chapter 16 Performance Analysis and Optimization of Fang Jiashan DCS Level 2 System
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    Chapter 17 Pickering Generating Station Primary Heat Transport Pressure Control Analysis During Boiler Steam Relief Valve Testing
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    Chapter 18 Pressurizer Water Level Control by Makeup and Letdown Flows Operating in Discontinued Model
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    Chapter 19 Qinshan 300 MW Nuclear Power Unit Condensed Water Dissolved Oxygen on the High Side Cause Analysis
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    Chapter 20 Research and Application of RtCM Techniques in CPR1000 Nuclear Power Plant
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    Chapter 21 Research on Technical Transformation of Lifting Equipment in Nuclear Power Plants
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    Chapter 22 Surface Corrosion Analysis of QF Control Rod Nitriding Tube
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    Chapter 23 The Corrosion Protection of Drum Strainer in Fuqing Nuclear Power Plant
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    Chapter 24 The Development of HOLLY Code and Single-Point Ex-core Detectors Calibration Method
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    Chapter 25 The Reasons for the Frequently Exceeded Pressure Drop of Resin Bed in Steam Generator Blowdown System
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    Chapter 26 The Research of High-Voltage Auxiliary Power System Neutral Point Grounding Modes Between the Nuclear Power Plant and Conventional Fossil Fuel Power Plant
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    Chapter 27 The Research of Selecting Scope of Maintenance Rule in the Key System of New Nuclear Power Plant
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    Chapter 28 The Research on the Model of Condense Regenerate Heater Under Off-design Conditions
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    Chapter 29 The Study of Extending AP1000 Spent Fuel Racks’ Storage Capacity
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    Chapter 30 Valves Maintainability Study on Nuclear Power Plant Design Stage
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    Chapter 31 An Improved Welding Process of Instrumentation Tubes on Nuclear Reactor Pressure Vessel
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    Chapter 32 Analysis of the Development of Nuclear Power Plant Construction Management Model and Management of Engineering Company and Owners
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    Chapter 33 Components Qualification for the Safe Operation of Nuclear Power Plants
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    Chapter 34 How to Build EQ System for Safety Classed Electrical Equipment Under the Modal of AE
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    Chapter 35 Modal Analysis of Anchored Cylindrical Liquid Storage Tanks
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    Chapter 36 Quality Control of Application Research on Supervision Planning of Hualong #1 Emergency Diesel Generator
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    Chapter 37 Quality Control of Sub-suppliers in EDG
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    Chapter 38 Research on Identification Test for Sealing Performance of Equipment on Containment Pressure Boundary
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    Chapter 39 Research on Problems of Ultrasonic Test for Reactor Vessel Internal During Manufacturing Process
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    Chapter 40 Risk Analysis on Holes Machining and Inspecting of RVI as One of the Main Equipments in Nuclear Island
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    Chapter 41 The Disbonding Mechanism Research of Submerged Arc Stainless Steel Strip Cladding
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    Chapter 42 Welding Process and Welding Consumable of Generation III Nuclear Island Main Equipment
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    Chapter 43 Application of Man–Machine System Analysis in the Process Control of Nuclear Fuel Manufacturing
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    Chapter 44 Decisioneering on Short- to Long-Term Nuclear Energy System Strategies DANESS v7.1
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    Chapter 45 Determination of Boron in ThO 2 Powder by ICP-AES After Matrix Separation Using Solvent Extraction
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    Chapter 46 Development and Validation of Methodology for Depletion Analysis of FHR at Equilibrium State
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    Chapter 47 Effects of Compressing Strength of Core Ball on Crushing Strength of Spherical Fuel Element
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    Chapter 48 Flow Effect on Core Burnup in a Molten Salt Reactor
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    Chapter 49 Key Parameter Measurements of the Low-Pressure Gas Discharge Plasmas Used for Studying the Ion Extraction Process
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    Chapter 50 Online Nondestructive Testing of Gadolinium Containing Fuel Rods
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    Chapter 51 Optimization of Thorium Utilization in Fluoride Salt-Cooled High-Temperature Reactor (FHR)
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    Chapter 52 Preparation of Zr-Doped ThO 2 Ceramic Microsphere By Sol–Gel Method
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    Chapter 53 R&D Base for Nuclear Fuel Manufacturing—CNNFC
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    Chapter 54 Research and Discussion of Development of Reliability Program About Nuclear Fuel Cycle
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    Chapter 55 Role and Position of PHWR in Nuclear Fuel Cycle in China
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    Chapter 56 Shielding Calculation Model and Simplified Analysis of the Spent Fuel Pool
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    Chapter 57 PBNC—2016 Technology Evolutions in MOX Fuel Reprocessing Plants
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    Chapter 58 The First AP1000 Fuel Fabrication Line in China
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    Chapter 59 The Important Aspects on the Protection of Occupational Exposure of the Spent Nuclear Fuel Reprocessing Facility
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    Chapter 60 The Method to Ascertain Time-Control Parameters of Reverse Fluidic Device Based on Level Feedback of Supply Tank
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    Chapter 61 The Microstructure and Characteristic Analysis of USW Welding
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    Chapter 62 Ultrasonic Test for Typical Defect of Zirconium Alloy Tube used in Nuclear Fuel Assembly
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    Chapter 63 A Deconvolution Algorithm for Gamma Spectrum Based on Energy Resolution Calibration
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    Chapter 64 A Potential Way of Co-60 Production in CANDU6 Reactors
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    Chapter 65 Base-Isolation Technology Investigation for SMR Nuclear Island Building
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    Chapter 66 Conceptual Design of High Temperature Water-Cooled Divertor Plasma-Facing Unit for Fusion Reactor
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    Chapter 67 Corrosion Resistance of Oxide Dispersion Strengthened Steel in Supercritical Water
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    Chapter 68 Design of a Thin-Film Neutron Detector Used for Personnel Dosimeter
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    Chapter 69 Development and Verification of Liquid-Fueled Molten Salt Reactor Analysis Code Based on RELAP5
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    Chapter 70 Emergency Strategy Research of MSLB Accident with Loss of Passive Residual Heat Removal for Small Modular Reactor
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    Chapter 71 Evaluation and Analysis of Forced Convection Heat Transfer Correlations for Supercritical Carbon Dioxide in Vertical Tubes
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    Chapter 72 Experimental Study on the Effects of Temperature and pH on the Deposition of Corrosion Products in Fusion Reactor
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    Chapter 73 Large-Fluence Laser-Driven Ion Beam for Inertial Fusion Ignition
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    Chapter 74 Lead Cooled Fast Reactor Core Physics Parameters Calculation Based on Monte Carlo Method
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    Chapter 75 Neutron Activation Analysis of Candidate Materials for High-Temperature Reactors
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    Chapter 76 Physics Analysis of Alternative Fuel Options for HTGR
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    Chapter 77 Preliminary Design of Oxygen Control and Purification System in Lead-Alloy Cooled Reactors
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    Chapter 78 R&D of the In-Vessel Materials for Future Magnetic Confinement Fusion Reactors at SWIP
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    Chapter 79 Research on Ionizing Effects in γ-Ray-Irradiated CMOS Pixel Image Sensor
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    Chapter 80 Scheme Research of Mars Surface Nuclear Reactor Power
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    Chapter 81 Seawater Desalination Technology Route and Analysis of Production Capacity for Large Commercial Nuclear Power Plant
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    Chapter 82 Structural Design and Verification of the CNFC-HTR New Fuel Transport Container
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    Chapter 83 Structure Design of Calorimeter of EAST-NBI System Using Thermal Inertia with Cooling Water
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    Chapter 84 Study of the Tritium Breeding Blanket in an Hybrid Fusion–Fission Transmutation System
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    Chapter 85 Tagged Neutron Method Analysis: A Technique for Explosives Detection and Identification
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    Chapter 86 Using Traveling Wave Reactor (TWR) Technology to Provide Globally Scalable and Sustainable, Carbon-Free Energy
Overall attention for this book and its chapters
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Title
Proceedings of The 20th Pacific Basin Nuclear Conference
Published by
Springer Singapore, January 2017
DOI 10.1007/978-981-10-2317-0
ISBNs
978-9-81-102316-3, 978-9-81-102317-0
Editors

Jiang, Hong

Mendeley readers

Mendeley readers

The data shown below were compiled from readership statistics for 16 Mendeley readers of this research output. Click here to see the associated Mendeley record.

Geographical breakdown

Country Count As %
Unknown 16 100%

Demographic breakdown

Readers by professional status Count As %
Student > Bachelor 3 19%
Professor 1 6%
Student > Ph. D. Student 1 6%
Lecturer 1 6%
Unknown 10 63%
Readers by discipline Count As %
Social Sciences 2 13%
Chemical Engineering 1 6%
Earth and Planetary Sciences 1 6%
Engineering 1 6%
Unknown 11 69%