聚变堆设计与核技术PDF|Epub|txt|kindle电子书版本网盘下载

聚变堆设计与核技术PDF格式电子书版下载

注意：本站所有压缩包均有解压码： 点击下载压缩包解压工具

上篇 聚变堆设计5

一、综 述5

Conceptual Design Activities of FDS Series Fusion Power Plants in China5

DEMO Development Strategy Based on China FPP Program14

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

A Way for Early Application of Fusion Technology25

Progress in Fusion-driven Hybrid System Studies in China36

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-Ⅱ65

Fusion-based Hydrogen Production Reactor and Its Material Selection79

Design Status and Development Strategy of China Liquid Lead-lithium Blankets and Related Material Technology90

Review of Blanket Designs for Advanced Fusion Reactors99

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-Ⅱ129

Comparison Analysis of 1D/2D/3D Neutronics Modeling for a Fusion Reactor135

Tritium Supply Assessment for ITER and Demonstration Power Plant144

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-Ⅱ164

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 Reactors192

Summary of the 1 st International Workshop on Environmental，Safety and Economic Aspects of Fusion Power220

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 Technologies247

Conceptual Design of the Fusion-Driven Subcritical System FDS-I262

The Fusion-Driven Hybrid System and Its Material Selection273

A low Aspect Ratio Tokamak Transmutation System287

Conceptual Study on Liquid Metal Center Conductor Post in Spherical Tokamak294

Reactors294

Conceptual Study on High Performance Blanket in a Spherical Tokamak Fusion-Driven Transmuter300

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 System315

Neutronics Analysis of Dual-Cooled Waste Transmutation Blanket for the FDS325

Analysis on Fuel Cycle Schemes in the Dual-Cooled Waste Transmutation Blanket for the FDS-I333

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 Reactor353

Preliminary Analysis of Liquid PbLi MHD Flow and Pressure Drop in DWT Blanket of FDS-I364

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-I377

Probabilistic Safety Assessment of the Dual-cooled Waste Transmutation Blanket for the FDS-I385

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 EAST424

Overview of Liquid Metal TBM Concepts and Programs437

Design Analysis of the China Dual-Functional Lead Lithium（DFLL）Test Blanket Module in ITER451

Neutronics Analysis for the Test Blanket Modules Proposed for EAST and ITER466

Preliminary Safety Analysis for the Chinese ITER Dual Functional Lead-Lithium Test Blanket Module474

五、设计工具和数据库489

CAD-Based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC489

Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor506

Development of Reliability and Probabilistic Safety Assessment Program RiskA516

Code Development and Validation for Analyzing Liquid Metal MHD Flow in Rectangular Duct530

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 HINEG559

Design and Analyses of Rotating Tritium Target System for High Intensity D-T Fusion Neutron Generator566

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 System586

Design of Personnel Radiation Safety Interlock System for High Intensity D-T Fusion Neutron Generator594

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 Application613

Recent Progress of R＆D Activities on Reduced Activation Ferritic/Martensitic Steels625

Status and Strategy of Fusion Materials Development in China642

Progress in Development of China Low Activation Martensitic Steel for Fusion Application655

Study of Irradiation Effects in China Low Activation Martensitic Steel CLAM663

Preliminary Analysis of Irradiation Effects on CLAM after Low Dose Neutron Irradiation671

Swelling of CLAM Steel Irradiated by Electron/Helium to 17.5 dpa with 10 appm He/dpa677

Latest Progress on R＆D of ITER DFLL-TBM in China682

Progress in Development of CLAM Steel and Fabrication of Small TBM in China690

Welding Techniques Development of CLAM Steel for Test Blanket Module699

Mechanical Properties and Microstructures of China Low Activation Martensitic Steel Compared with JLF-1707

Tensile Properties of CLAM Steel Irradiated up to 20.1 dpa in STIP-V715

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 Testing738

Design Analysis of DRAGON-Ⅳ PbLi Loop746

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 PbLi771

Corrosion Experiment in the First Liquid Metal PbLi Loop of China779

Progress in Compatibility Experiments on Lead-Lithium with Candidate Structural Materials for Fusion in China785

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes under Uniform Magnetic Field794