Proceedings of The 20th Pacific Basin Nuclear Conference: Volume 2

Front Matter....Pages i-xiv
Front Matter....Pages 1-1
A Study of AP1000 Nuclear Power Plant SGTR Event Processing Strategy....Pages 3-13
A Summary of the Guidelines on the Evaluation of V&V Tools for Safety Digital I&C Software in Nuclear Power Plant Systems....Pages 15-21
Analysis and Handling of Turbine Eccentricity Anomaly....Pages 23-30
Analysis and Summarization of Continuous Spray Test on Pressurizer of Fuqing Nuclear Power Plant Unit 1....Pages 31-37
Analysis of the CRDM Coils Current Interference and the Abnormal Display of Rod Position in RGL System....Pages 39-47
Application of Key Interlock in HUALONG-I 3rd Nuclear Unit....Pages 49-55
Charpy Impact Properties of Electron Beam Welded V-4Cr-4Ti Alloy....Pages 57-65
Conclusion of the Test of Fujian Fuqing Nuclear Power Plant Unit 1 Determination of Reactor Coolant Flow on the Basis of the Heat Balance....Pages 67-73
Exceptional Shut Down During Load Test of Emergency Diesel Generator....Pages 75-80
Fangjiashan Auxiliary Transformer Low-Voltage Side of Three-Phase Voltage Imbalance Analysis....Pages 81-92
Design for High Level Layout and Control of Nuclear Island HVAC Based on DCS Technique....Pages 93-99
Improvements to CANDU6 Reactor Power Control Programs....Pages 101-112
Main Control Room Design of Advanced Nuclear Reactor....Pages 113-120
Material Substitute Research of the Main Pipeline Bracket Protection Cushion in CPR1000 NPP....Pages 121-134
Nuclear Steam Generator Water Level Control Based on DFNN....Pages 135-151
Performance Analysis and Optimization of Fang Jiashan DCS Level 2 System....Pages 153-166
Pickering Generating Station Primary Heat Transport Pressure Control Analysis During Boiler Steam Relief Valve Testing....Pages 167-180
Pressurizer Water Level Control by Makeup and Letdown Flows Operating in Discontinued Model....Pages 181-187
Qinshan 300 MW Nuclear Power Unit Condensed Water Dissolved Oxygen on the High Side Cause Analysis....Pages 189-199
Research and Application of RtCM Techniques in CPR1000 Nuclear Power Plant....Pages 201-214
Front Matter....Pages 1-1
Research on Technical Transformation of Lifting Equipment in Nuclear Power Plants....Pages 215-221
Surface Corrosion Analysis of QF Control Rod Nitriding Tube....Pages 223-230
The Corrosion Protection of Drum Strainer in Fuqing Nuclear Power Plant....Pages 231-236
The Development of HOLLY Code and Single-Point Ex-core Detectors Calibration Method....Pages 237-246
The Reasons for the Frequently Exceeded Pressure Drop of Resin Bed in Steam Generator Blowdown System....Pages 247-255
The Research of High-Voltage Auxiliary Power System Neutral Point Grounding Modes Between the Nuclear Power Plant and Conventional Fossil Fuel Power Plant....Pages 257-276
The Research of Selecting Scope of Maintenance Rule in the Key System of New Nuclear Power Plant....Pages 277-283
The Research on the Model of Condense Regenerate Heater Under Off-design Conditions....Pages 285-293
The Study of Extending AP1000 Spent Fuel Racks’ Storage Capacity....Pages 295-305
Valves Maintainability Study on Nuclear Power Plant Design Stage....Pages 307-313
Front Matter....Pages 315-315
An Improved Welding Process of Instrumentation Tubes on Nuclear Reactor Pressure Vessel....Pages 317-326
Analysis of the Development of Nuclear Power Plant Construction Management Model and Management of Engineering Company and Owners....Pages 327-335
Components Qualification for the Safe Operation of Nuclear Power Plants....Pages 337-349
How to Build EQ System for Safety Classed Electrical Equipment Under the Modal of AE....Pages 351-361
Modal Analysis of Anchored Cylindrical Liquid Storage Tanks....Pages 363-368
Quality Control of Application Research on Supervision Planning of Hualong #1 Emergency Diesel Generator....Pages 369-382
Quality Control of Sub-suppliers in EDG....Pages 383-392
Research on Identification Test for Sealing Performance of Equipment on Containment Pressure Boundary....Pages 393-402
Research on Problems of Ultrasonic Test for Reactor Vessel Internal During Manufacturing Process....Pages 403-411
Risk Analysis on Holes Machining and Inspecting of RVI as One of the Main Equipments in Nuclear Island....Pages 413-423
Front Matter....Pages 315-315
The Disbonding Mechanism Research of Submerged Arc Stainless Steel Strip Cladding....Pages 425-434
Welding Process and Welding Consumable of Generation III Nuclear Island Main Equipment....Pages 435-450
Front Matter....Pages 451-451
Application of Man–Machine System Analysis in the Process Control of Nuclear Fuel Manufacturing....Pages 453-462
Decisioneering on Short- to Long-Term Nuclear Energy System Strategies DANESS v7.1....Pages 463-476
Determination of Boron in ThO2 Powder by ICP-AES After Matrix Separation Using Solvent Extraction....Pages 477-483
Development and Validation of Methodology for Depletion Analysis of FHR at Equilibrium State....Pages 485-492
Effects of Compressing Strength of Core Ball on Crushing Strength of Spherical Fuel Element....Pages 493-501
Flow Effect on Core Burnup in a Molten Salt Reactor....Pages 503-520
Key Parameter Measurements of the Low-Pressure Gas Discharge Plasmas Used for Studying the Ion Extraction Process....Pages 521-531
Online Nondestructive Testing of Gadolinium Containing Fuel Rods....Pages 533-550
Optimization of Thorium Utilization in Fluoride Salt-Cooled High-Temperature Reactor (FHR)....Pages 551-560
Preparation of Zr-Doped ThO2 Ceramic Microsphere By Sol–Gel Method....Pages 561-568
R&D Base for Nuclear Fuel Manufacturing—CNNFC....Pages 569-572
Research and Discussion of Development of Reliability Program About Nuclear Fuel Cycle....Pages 573-579
Role and Position of PHWR in Nuclear Fuel Cycle in China....Pages 581-590
Shielding Calculation Model and Simplified Analysis of the Spent Fuel Pool....Pages 591-599
PBNC—2016 Technology Evolutions in MOX Fuel Reprocessing Plants....Pages 601-608
The First AP1000 Fuel Fabrication Line in China....Pages 609-616
The Important Aspects on the Protection of Occupational Exposure of the Spent Nuclear Fuel Reprocessing Facility....Pages 617-625
The Method to Ascertain Time-Control Parameters of Reverse Fluidic Device Based on Level Feedback of Supply Tank....Pages 627-637
Front Matter....Pages 451-451
The Microstructure and Characteristic Analysis of USW Welding....Pages 639-653
Ultrasonic Test for Typical Defect of Zirconium Alloy Tube used in Nuclear Fuel Assembly....Pages 655-663
Front Matter....Pages 665-665
A Deconvolution Algorithm for Gamma Spectrum Based on Energy Resolution Calibration....Pages 667-677
A Potential Way of Co-60 Production in CANDU6 Reactors....Pages 679-689
Base-Isolation Technology Investigation for SMR Nuclear Island Building....Pages 691-703
Conceptual Design of High Temperature Water-Cooled Divertor Plasma-Facing Unit for Fusion Reactor....Pages 705-714
Corrosion Resistance of Oxide Dispersion Strengthened Steel in Supercritical Water....Pages 715-723
Design of a Thin-Film Neutron Detector Used for Personnel Dosimeter....Pages 725-730
Development and Verification of Liquid-Fueled Molten Salt Reactor Analysis Code Based on RELAP5....Pages 731-739
Emergency Strategy Research of MSLB Accident with Loss of Passive Residual Heat Removal for Small Modular Reactor....Pages 741-751
Evaluation and Analysis of Forced Convection Heat Transfer Correlations for Supercritical Carbon Dioxide in Vertical Tubes....Pages 753-768
Experimental Study on the Effects of Temperature and pH on the Deposition of Corrosion Products in Fusion Reactor....Pages 769-774
Large-Fluence Laser-Driven Ion Beam for Inertial Fusion Ignition....Pages 775-782
Lead Cooled Fast Reactor Core Physics Parameters Calculation Based on Monte Carlo Method....Pages 783-791
Neutron Activation Analysis of Candidate Materials for High-Temperature Reactors....Pages 793-800
Physics Analysis of Alternative Fuel Options for HTGR....Pages 801-811
Preliminary Design of Oxygen Control and Purification System in Lead-Alloy Cooled Reactors....Pages 813-824
R&D of the In-Vessel Materials for Future Magnetic Confinement Fusion Reactors at SWIP....Pages 825-837
Research on Ionizing Effects in γ-Ray-Irradiated CMOS Pixel Image Sensor....Pages 839-852
Scheme Research of Mars Surface Nuclear Reactor Power....Pages 853-864
Front Matter....Pages 665-665
Seawater Desalination Technology Route and Analysis of Production Capacity for Large Commercial Nuclear Power Plant....Pages 865-872
Structural Design and Verification of the CNFC-HTR New Fuel Transport Container....Pages 873-881
Structure Design of Calorimeter of EAST-NBI System Using Thermal Inertia with Cooling Water....Pages 883-893
Study of the Tritium Breeding Blanket in an Hybrid Fusion–Fission Transmutation System....Pages 895-903
Tagged Neutron Method Analysis: A Technique for Explosives Detection and Identification....Pages 905-917
Using Traveling Wave Reactor (TWR) Technology to Provide Globally Scalable and Sustainable, Carbon-Free Energy....Pages 919-936