一、革新核能安全理念 3
革新型核能系统安全研究的回顾与探讨 3
Identification of Safety Gaps for Fusion Demonstration Reactors 10
福岛核电厂事故的影响与思考 37
Public Acceptance of Constructing Coastal/Inland Nuclear Power Plants in Post-Fukushima China 44
聚变堆安全特性评价研究 62
二、安全方法学与评价 79
1 方法学 79
先进核能系统设计分析软件与数据库研发进展 79
CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC 91
CAD-based Interface Programs for Fusion Neutron Transport Simulation 108
A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Numerical Calculation in Curvilinear Geometries 119
蒙特卡罗粒子输运计算自动建模程序系统的研究与发展 130
多物理耦合分析自动建模软件SuperMC/MCAM5.2设计与实现 140
核与辐射安全仿真系统SuperMC/RVIS2.3研发与应用 148
大型集成多功能中子学计算与分析系统VisualBUS的研究与发展 159
大型集成概率安全分析软件系统的研究与发展 171
Development of Reliability and Probabilistic Safety Assessment Program RiskA 180
核能信息化与虚拟核电厂应用实践 194
先进核能软件发展与核信息学实践 204
关于核聚变研究信息化的实践与思考 217
2 概率安全评价 229
Development and Application of a Risk Monitor for Nuclear Power Plant 229
秦山三期重水堆核电厂风险监测器研发进展 237
Architecture and Design of Third Qinshan Nuclear Power Plant Risk Monitor 247
A Nuclear Power Plant Risk Monitor Based on Cloud Computing 254
Risk Monitor RiskAngel for Risk-informed Applications in Nuclear Power Plants 262
Development and Validation of Instantaneous Risk Model in Nuclear Power Plant’s Risk Monitor 275
Fault-tree-based Instantaneous Risk Computing Core in Nuclear Power Plant Risk Monitor 282
A Variable Ordering Heuristic based on Zero-Suppressed Binary Decision Diagrams 298
Verification of RiskA Calculation Engine Based on Open-PSA Platform 306
A Parallel Manipulation Method for Zero-suppressed Binary Decision Diagram 314
Processing of Switching Events Sets in Reliability and Probabilistic Safety Assessment Program RiskA 320
A New Decomposition Algorithm for Complex Voting Gates Processing in Qualitative Fault Tree Analysis 327
Asymmetrical Common-Cause Failures Analysis Method Applied in Fusion Reactors 339
Efficient Reduction and Modularization for Large Fault Trees Stored by Pages 353
Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor 362
3 事故分析 375
Benchmark of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC on Beam Interruptions in XADS 375
Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS Transient Simulation 384
Transient Analyses on Loss of Heat Sink and Overpower Transient of Natural Circulation LBE-cooled Fast Reactor 400
Comparison of transient analysis of LBE-cooled Fast Reactor and ADS under Loss of Heat Sink Accident 414
Preliminary Investigation on the Primary Heat Exchanger Lower Head Rupture Accident of Forced Circulation LBE-cooled Fast Reactor 427
Thermal and Stress Analysis of Window Target for Accelerator-driven Sub-critical System During Beam Trip Transients 439
Development and Testing of Multi-group Library with Correction of Self-shielding Effects in Fusion-fission Hybrid Reactor 452
Assessment of RVACS Performance for Small Size Lead-cooled Fast Reactor 460
三、典型工程应用 479
1 聚变堆应用 479
Neutronics Safety Analysis in Severe Transients of the Dual-cooled Waste Transmutation Blanket for the FDS-Ⅰ 479
Preliminary Transient Thermal Analysis for Safety of the Dual-cooled Waste Transmutation Blanket for the FDS-Ⅰ 487
Probabilistic Safety Assessment of the Dual-cooled Waste Transmutation Blanket for the FDS-Ⅰ 494
Tritium Safety Assessment on High Temperature Liquid Blanket for Fusion-Based Hydrogen Production Reactor FDS-Ⅲ 501
基于最小化发电成本的聚变驱动次临界堆参数优化分析 509
Preliminary Leakage Reliability Analysis of DFLL-TBM based on a Combinational Approach 522
Selection of Bounding Events for ITER DFLL-TBM Safety Analysis 530
Failure Modes and Effects Analysis on ITER DFLL-TBM System 538
Preliminary RAMI Analysis of DFLL TBS for ITER 545
Preliminary Tritium Safety Analysis on China DFLL-TBM for ITER 556
Reliability Data Analysis for Tritium Extraction System Pipes of CN HCCB TBM 565
2 裂变堆应用 579
Preliminary Safety Analysis of China Lead Alloy Cooled Research Reactor CLEAR-Ⅰ 579
Preliminary Simulation of Fuel Dispersion in a Lead-Bismuth Eutectic(LBE)-cooled Research Reactor 590
Preliminary Source Term and Consequence Assessment of Primary Cover Gas Leakage Accident for CLEAR-Ⅰ 603
Preliminary Radioactive Source Term Analysis for Normal Operation of CLEAR-Ⅰ 614
Preliminary Analysis of Source Terra for Primary Coolant System of China Lead-based Research Reactor（CLEAR-Ⅰ） 620
Preliminary Analysis of Polonium-210 Contamination for China LEAd-based Research Reactor 626
Fuel Cladding Integrity Analysis During Beam Trip Transient for China Lead-based Demonstration Reactor 635
基于响应面拟合方法中国铅基研究实验堆非能动余热排出系统可靠性分析 649