Proceedings of The 20th Pacific Basin Nuclear Conference: Volume 1

Front Matter....Pages i-xiv
Front Matter....Pages 1-1
3D Finite Element Analysis for Outlet Nozzle....Pages 3-11
A CHF Correlation and Flow Pattern Observation on a Downward-Facing Boiling Surface....Pages 13-20
A Mathematical Model to Calculate the Minimum Acceptable Station Blackout Duration Capability of PWR Nuclear Power Plants....Pages 21-30
A Review of Study and Design Improvement of Natural Circulation-Based Heat Removal Systems....Pages 31-45
A Seismic Design Method for Safety-Related Instrument Line in ACP1000....Pages 47-53
A Simulation-Based Dynamic Approach for External Flooding Analysis in Nuclear Power Plants....Pages 55-69
Advanced Large PWR LB-LOCA BEPU Analysis with RELAP5-DAKOTA....Pages 71-79
An Investigation of FLEX Implementation in Maanshan NPP by Using MAAP 5....Pages 81-96
An Overview of Severe Accident Approach at EDF—Contribution of R&D Programs....Pages 97-117
Analysis and Improvement for External Occupational Expose in Nuclear Power Plants....Pages 119-125
Analysis and Research of ACP100 Turbine Protection System....Pages 127-137
Analysis of a Severe Accident Initiated By SBLOCA Utilizing MELCOR 2.1 in Gen-III Large PWR....Pages 139-149
Analysis of Fuel Rod Behavior Under Steady State and Transient Condition by Modification of THEATRe Code....Pages 151-162
Analysis of Key Factors for Nuclear Power Plant Emergency....Pages 163-170
Analysis of the Effect of the Primary Shield Structures on Dose Rates in the Operating Floor....Pages 171-180
Analysis on the Main Safety Problems of Treatment and Storage Systems of High-Level Liquid Wastes in Nuclear Fuel Reprocessing Plant....Pages 181-193
Annular Flow Interfacial Shear Stress in Pipes....Pages 195-201
CANDU-6 Response on Extreme Conditions Combined with SBO, LUHS, and Natural Disasters....Pages 203-212
Conceptual Design of Integral Test Facility for Hualong One....Pages 213-221
Consideration on the Usability of Equipment for Severe Accident Conditions....Pages 223-230
Front Matter....Pages 1-1
Containment Venting During Severe Accident: Reasons and Consequences....Pages 231-238
Sensitivity and Uncertainty Analysis of a SCWR from Monte Carlo Simulations....Pages 239-252
Design and Research of Nuclear Power Plant Emergency Communication....Pages 253-262
Design Extension Conditions: Concept and Its Application to Operating Reactor in Canada....Pages 263-275
Development and Application of Differential Pressure Protection Device for Classified Pump Inlet Strainer of Pressurized Water Reactor....Pages 277-284
Development of a Shutdown PSA Model for the TQNPC CANDU Reactor....Pages 285-294
Development of a Simplified Model for the Passive Containment Cooling System....Pages 295-307
Effect of Oxygenation During Cold Shutdown on Source Term for Radiation Shielding Design of RHR System....Pages 309-315
Experimental and Numerical Simulation Study on Multilayer Cable Trays Fire Under Mechanically Ventilated Conditions....Pages 317-325
Experimental Investigation on the Optimization of ADS Sparger Arrangement in IRWST of AP1000 Plant....Pages 327-338
Experimental Study on Heat Transfer Characteristics of Separated Type Heat Pipe....Pages 339-350
Fire Compartment and Fire Barrier Evaluation in the NPP Fire PSA....Pages 351-363
Human Reliability Analysis of Nuclear Power Plants Under Fire Scenarios....Pages 365-375
Internal Exposure Study for Nuclear Power Plant Accident and Emergency Conditions....Pages 377-383
Lessons Learned from Fukushima—Applied to Emergency Preparedness in Taiwan....Pages 385-397
Localization of the Hot Spots in the Pebble Bed HTR....Pages 399-409
Management Method for Improving the Ability of Preventing Human Error in Nuclear Power Plant....Pages 411-417
Modeling Fukushima Dose Consequences with EPZDose....Pages 419-427
Neutron and Gamma-Ray Deep Penetration Shielding Calculation of Lead-Cooled Fast Reactor....Pages 429-436
Nuclear and Radiation Accident Emergency Technical Center in China....Pages 437-444
Front Matter....Pages 1-1
Numerical Investigation of Passively Cooled Steam Generator Natural Circulation Using RELAP5 Code....Pages 445-452
Numerical Simulation of Cavitation Phenomenon in Thin and Long Orifices....Pages 453-459
Quantitative Analysis of Safety Margin Reduction of Power Uprate in MBLOCA....Pages 461-479
Research and Development of Core Damage Assessment System....Pages 481-489
Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code....Pages 491-499
Research of Testing for Scientific Computing Software in the Area of Nuclear Power Based on Metamorphic Testing....Pages 501-512
Seismic Margin Analysis of In-Service Nuclear Power Plant....Pages 513-524
Research on Severe Accident Management Strategies for CPR1000 NPP Under Refueling Cooling Mode....Pages 525-534
Research and Application of the Environment Factor of Loss of Offsite Power....Pages 535-544
Scaling Analysis of Steam Generator During Natural Circulation Phase Under Station Blackout Accident....Pages 545-553
Seismic Margin Assessment of Three Operating Nuclear Power Plants in Taiwan from Regulatory Prospective....Pages 555-563
Selected Containment Systems for Severe Accident Mitigation....Pages 565-570
Severe Accident Progression and Release Categories Analysis in Application to EPZ Evaluation for a BWR-4 NPP....Pages 571-581
Scaling Analysis of Fluid Properties for Natural Circulation Phenomena Under Station Blackout Accident....Pages 583-593
Spent Fuel Cladding Performance Analysis Under Spent Fuel Pool Boiling-off Accident....Pages 595-599
Study of Potential for In-Vessel Retention Through External Reactor Vessel Flooding: Code Comparison....Pages 601-615
Study on Fire Ignition Frequency of Nuclear Power Plant....Pages 617-626
Study on Human Error Under Digital MCR Environment of Nuclear Power Plant....Pages 627-634
Study on Longitudinal Seismic Response of Underground Gallery Based on ANSYS....Pages 635-645
Study on New Considerations of Defence in Depth Strategy for Nuclear Power Plants....Pages 647-661
Front Matter....Pages 1-1
Technical Insights and Implementation Suggestions for “Practical Elimination of Large Radioactive Release by Design”....Pages 663-672
The Analysis of Initiating Events in PSA for TMSR....Pages 673-680
The Application of Formal Verification on the FPGA of Instrument and Control Systems in Nuclear Power Plants....Pages 681-687
The Cyber Security Evaluation of China’s Nuclear Power Plant DCS System....Pages 689-700
Effect of Head Loss on Flow Rate of Spray System and Containment Pressure....Pages 701-710
The Establishment and Simulation of TRACE/FRAPTRAN/MELCOR/SNAP Model for Chinshan Nuclear Power Plant Ultimate Response Guideline....Pages 711-731
The Radiation Protection Cloud Service System in Taiwan....Pages 733-738
The Simulation of Thermal Hydraulic of the Lead-Cooled Fast Reactor....Pages 739-747
Uncertainty Study of TMSR-SF Loss of Offsite Power Accident....Pages 749-764
Front Matter....Pages 765-765
Cultural Factors in Risk Perception: Observations from Interactions with Aboriginal Communities....Pages 767-785
Communication with the Public of the New Nuclear Power Project, Science Popularization in First....Pages 787-788
Nuclear Power Public Communication and Local Cultural Integration Practice....Pages 789-799
Strategy on Public Acceptance of Nuclear Power for the Newcomer Countries....Pages 801-809
The Global Acceptance Proven Model Developed....Pages 811-813
The Public Communication....Pages 815-824
The Public Perception of Risk with Reference to Nuclear Power....Pages 825-835
To Be a Good Neighbor for the Public....Pages 837-840
Front Matter....Pages 841-841
A Dissertation on Economic Efficiency of SMR....Pages 843-849
Analysis on Engineering Cost Estimation Method for Overseas NPP Projects....Pages 851-856
Discussion About Nuclear Power EPC Model....Pages 857-874
Front Matter....Pages 841-841
Discussion on Assembly Technology of AP1000 Nuclear Power Plant CA20 Large Structural Module....Pages 875-880
Earned Value Management for China AP1000/CAP1400 Nuclear Power Plant Construction Projects....Pages 881-890
Preliminary Study of Technical and Economic Work for Chinese NPP Export Projects....Pages 891-899
Research on Chinese Nuclear Power Cost Control Under the Perspective of Regulation....Pages 901-909
Sensitivity Analysis for Cold End System Optimization of a Nuclear Power Plant....Pages 911-922
Shop Drawing Management of Nuclear Power Plant Engineering....Pages 923-928
Study on the Method and Its Application of Performance Evaluation of Nuclear Power Project Construction Based on the Method of Down-Top Resources Collection....Pages 929-939
The Summary and Research on Nuclear Island Construction and Erection Cost Management of AP1000 Nuclear Power Plant Project....Pages 941-953
The Usage and Research of “Potential Trend Notice” in Sanmen AP1000 Nuclear Power Plant Construction Project Change Management....Pages 955-964
The Work Day Determination Method of the New “Nuclear Power Plant Construction Budget Quota” Based on the Work Day of “National General Budget Quota”....Pages 965-976
To Promote Engineering Surplus Materials Allocation Timely Ratio of Fang Jiashan Project Department....Pages 977-988