聚变堆设计与核技术PDF电子书下载

上篇 聚变堆设计 5

一、综 述 5

Conceptual Design Activities of FDS Series Fusion Power Plants in China 5

DEMO Development Strategy Based on China FPP Program 14

A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System： 25

A Way for Early Application of Fusion Technology 25

Progress in Fusion-driven Hybrid System Studies in China 36

二、聚变堆设计 51

1 聚变堆概念与包层设计 51

聚变发电反应堆概念设计研究 51

Conceptual Design of the China Fusion Power Plant FDS-Ⅱ 65

Fusion-based Hydrogen Production Reactor and Its Material Selection 79

Design Status and Development Strategy of China Liquid Lead-lithium Blankets and Related Material Technology 90

Review of Blanket Designs for Advanced Fusion Reactors 99

聚变堆增殖包层概念特征比较研究 117

2 中子学与燃料循环 129

Preliminary Neutronics Design of the Dual-cooled Lead Lithium Blanket for FDS-Ⅱ 129

Comparison Analysis of 1D/2D/3D Neutronics Modeling for a Fusion Reactor 135

Tritium Supply Assessment for ITER and Demonstration Power Plant 144

3 结构与热工水力学 157

聚变发电反应堆双冷液态铅锂包层模块结构设计与分析 157

Preliminary Thermal-hydraulics Design of the Dual-cooled Lead Lithium Blanket for FDS-Ⅱ 164

聚变发电反应堆双冷铅锂包层液态金属流动MHD效应计算与分析 171

4 安全、环境与经济性 181

聚变堆安全特性评价研究 181

Identification of Safety Gaps for Fusion Demonstration Reactors 192

Summary of the 1 st International Workshop on Environmental，Safety and Economic Aspects of Fusion Power 220

聚变发电反应堆双冷液态铅锂包层的初步概率安全分析 230

具有双冷液态铅锂包层的聚变动力电站经济性初步分析 236

三、聚变裂变混合堆设计 247

1 混合堆概念及包层设计 247

A Fusion-Driven Subcritical System Concept Based on Viable Technologies 247

Conceptual Design of the Fusion-Driven Subcritical System FDS-I 262

The Fusion-Driven Hybrid System and Its Material Selection 273

A low Aspect Ratio Tokamak Transmutation System 287

Conceptual Study on Liquid Metal Center Conductor Post in Spherical Tokamak 294

Reactors 294

Conceptual Study on High Performance Blanket in a Spherical Tokamak Fusion-Driven Transmuter 300

2 中子学与燃料循环 309

聚变驱动次临界堆输运燃耗计算二维效应分析研究 309

Neutronics Analysis and Optimization for Fusion Driven Subcritical Spent Fuel Burning System 315

Neutronics Analysis of Dual-Cooled Waste Transmutation Blanket for the FDS 325

Analysis on Fuel Cycle Schemes in the Dual-Cooled Waste Transmutation Blanket for the FDS-I 333

Design and Analysis on Tritium System of Multi-Functional Experimental Fusion-fission Hybrid Reactor （FDS-MFX） 342

3 结构与热工水力学 353

Thermal-hydraulic Optimization of Water-cooled Center Conductor Post for Spherical Tokamaks Reactor 353

Preliminary Analysis of Liquid PbLi MHD Flow and Pressure Drop in DWT Blanket of FDS-I 364

4 安全、环境与经济性 377

Preliminary Transient Thermal Analysis for Safety of the Dual-cooled WasteTransmutation Blanket for the FDS-I 377

Probabilistic Safety Assessment of the Dual-cooled Waste Transmutation Blanket for the FDS-I 385

Activation Analysis and Waste Management for Blanket Materials of Multi-functional Experimental Fusion-fission Hybrid Reactor（FDS-MFX） 392

四、液态铅锂实验包层 407

ITER中国液态铅锂实验包层模块设计研究与实验策略 407

Conceptual Design and Testing Strategy of a Dual Functional Lead Lithium Test Blanket Module in ITER and EAST 424

Overview of Liquid Metal TBM Concepts and Programs 437

Design Analysis of the China Dual-Functional Lead Lithium（DFLL）Test Blanket Module in ITER 451

Neutronics Analysis for the Test Blanket Modules Proposed for EAST and ITER 466

Preliminary Safety Analysis for the Chinese ITER Dual Functional Lead-Lithium Test Blanket Module 474

五、设计工具和数据库 489

CAD-Based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC 489

Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor 506

Development of Reliability and Probabilistic Safety Assessment Program RiskA 516

Code Development and Validation for Analyzing Liquid Metal MHD Flow in Rectangular Duct 530

HENDL 2.1/CG数据库的临界基准测试与分析 541

下篇 聚变核技术 551

一、强流氘氚聚变中子源 551

强流氘氚聚变中子源HINEG设计研究 551

Development of High Intensity D-T Fusion Neutron Generator HINEG 559

Design and Analyses of Rotating Tritium Target System for High Intensity D-T Fusion Neutron Generator 566

氘氚聚变中子发生器旋转氚靶传热特性分析研究 578

Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System 586

Design of Personnel Radiation Safety Interlock System for High Intensity D-T Fusion Neutron Generator 594

基于GDT的14 MeV中子源初步设计研究 603

二、抗辐照结构材料 613

Development Status of CLAM Steel for Fusion Application 613

Recent Progress of R＆D Activities on Reduced Activation Ferritic/Martensitic Steels 625

Status and Strategy of Fusion Materials Development in China 642

Progress in Development of China Low Activation Martensitic Steel for Fusion Application 655

Study of Irradiation Effects in China Low Activation Martensitic Steel CLAM 663

Preliminary Analysis of Irradiation Effects on CLAM after Low Dose Neutron Irradiation 671

Swelling of CLAM Steel Irradiated by Electron/Helium to 17.5 dpa with 10 appm He/dpa 677

Latest Progress on R＆D of ITER DFLL-TBM in China 682

Progress in Development of CLAM Steel and Fabrication of Small TBM in China 690

Welding Techniques Development of CLAM Steel for Test Blanket Module 699

Mechanical Properties and Microstructures of China Low Activation Martensitic Steel Compared with JLF-1 707

Tensile Properties of CLAM Steel Irradiated up to 20.1 dpa in STIP-V 715

三、冷却剂／增殖剂技术 727

中国系列液态铅锂实验回路设计与研发进展 727

R＆D of DRAGON Series Lead-Lithium Loops for Material and Blanket Technology Testing 738

Design Analysis of DRAGON-Ⅳ PbLi Loop 746

ITER中国液态铅锂实验回路中的氚技术 754

聚变堆液态金属铅锂包层多功能涂层研发 762

Compatibility of Atmospheric Plasma Sprayed Al2 O3 Coatings on CLAM with Liquid PbLi 771

Corrosion Experiment in the First Liquid Metal PbLi Loop of China 779

Progress in Compatibility Experiments on Lead-Lithium with Candidate Structural Materials for Fusion in China 785

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes under Uniform Magnetic Field 794