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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 Reactors10

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 China44

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 SuperMC91

CAD-based Interface Programs for Fusion Neutron Transport Simulation108

A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Numerical Calculation in Curvilinear Geometries119

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 RiskA180

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 Plant229

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 Monitor247

A Nuclear Power Plant Risk Monitor Based on Cloud Computing254

Risk Monitor RiskAngel for Risk-informed Applications in Nuclear Power Plants262

Development and Validation of Instantaneous Risk Model in Nuclear Power Plant’s Risk Monitor275

Fault-tree-based Instantaneous Risk Computing Core in Nuclear Power Plant Risk Monitor282

A Variable Ordering Heuristic based on Zero-Suppressed Binary Decision Diagrams298

Verification of RiskA Calculation Engine Based on Open-PSA Platform306

A Parallel Manipulation Method for Zero-suppressed Binary Decision Diagram314

Processing of Switching Events Sets in Reliability and Probabilistic Safety Assessment Program RiskA320

A New Decomposition Algorithm for Complex Voting Gates Processing in Qualitative Fault Tree Analysis327

Asymmetrical Common-Cause Failures Analysis Method Applied in Fusion Reactors339

Efficient Reduction and Modularization for Large Fault Trees Stored by Pages353

Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor362

3 事故分析375

Benchmark of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC on Beam Interruptions in XADS375

Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS Transient Simulation384

Transient Analyses on Loss of Heat Sink and Overpower Transient of Natural Circulation LBE-cooled Fast Reactor400

Comparison of transient analysis of LBE-cooled Fast Reactor and ADS under Loss of Heat Sink Accident414

Preliminary Investigation on the Primary Heat Exchanger Lower Head Rupture Accident of Forced Circulation LBE-cooled Fast Reactor427

Thermal and Stress Analysis of Window Target for Accelerator-driven Sub-critical System During Beam Trip Transients439

Development and Testing of Multi-group Library with Correction of Self-shielding Effects in Fusion-fission Hybrid Reactor452

Assessment of RVACS Performance for Small Size Lead-cooled Fast Reactor460

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-Ⅰ479

Preliminary Transient Thermal Analysis for Safety of the Dual-cooled Waste Transmutation Blanket for the FDS-Ⅰ487

Probabilistic Safety Assessment of the Dual-cooled Waste Transmutation Blanket for the FDS-Ⅰ494

Tritium Safety Assessment on High Temperature Liquid Blanket for Fusion-Based Hydrogen Production Reactor FDS-Ⅲ501

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 Approach522

Selection of Bounding Events for ITER DFLL-TBM Safety Analysis530

Failure Modes and Effects Analysis on ITER DFLL-TBM System538

Preliminary RAMI Analysis of DFLL TBS for ITER545

Preliminary Tritium Safety Analysis on China DFLL-TBM for ITER556

Reliability Data Analysis for Tritium Extraction System Pipes of CN HCCB TBM565

2 裂变堆应用579

Preliminary Safety Analysis of China Lead Alloy Cooled Research Reactor CLEAR-Ⅰ579

Preliminary Simulation of Fuel Dispersion in a Lead-Bismuth Eutectic(LBE)-cooled Research Reactor590

Preliminary Source Term and Consequence Assessment of Primary Cover Gas Leakage Accident for CLEAR-Ⅰ603

Preliminary Radioactive Source Term Analysis for Normal Operation of CLEAR-Ⅰ614

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 Reactor626

Fuel Cladding Integrity Analysis During Beam Trip Transient for China Lead-based Demonstration Reactor635

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