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Design and testing of the Fusion Virtual Assembly System FVAS 1.0

Design and testing of the Fusion Virtual Assembly System FVA...

引用

第十二届反应堆数值计算与粒子输运学术会议

作者： the FDS Team Institute of Plasma Physics Chinese Academy of Sciences

This paper presents the Fusion Virtual Assembly System FVAS 1.0 which makes possible engineering application for assem- blies of large-scale complex nuclear *** system focuses on utilizing a desktop virtual environment tightly coupled with commercial Computer Aided Design (CAD) systems,and is designed to support assembly planning,evaluation,demon- stration,and training,and to work on personal computer (PC) *** features of FVAS include:(1) automatic assembly modeling,(2) separation of display scene and collision detection scene,(3) multi-way assembly planning,(4) records and replays of assembly *** paper describes the system architecture,features and capabilities of *** tests conducted using real-world engineering models are also described.

关键词： Virtual assembly Collision detection Virtual roaming Nuclear facility

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A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System:A Way for Early Application of Fusion Technology

A Fusion Neutron Source Driven Sub-Critical Nuclear Energy S...

引用

第十二届反应堆数值计算与粒子输运学术会议

作者：吴宜灿 Institute of Plasma Physics Chinese Academy of Sciences

This paper proposes a sub-critical nuclear energy system driven by fusion neutron source,FDS,which can be used to transmute long-lived radioactive wastes and to produce fissile nuclear fuel as a way for early application of fusion *** necessity and feasibility to develop that system in China are illustrated on the basis of prediction of the demand of energy source in the first half of the 21th century,the status of current fission energy supply and the progress in fusion technology in the *** characteristics of fusion neutron driver and the potential for transmutation of long-lived nuclear wastes and breeding of fissile nuclear fuel in a blanket are analyzed.A scenario of development steps is proposed.

关键词： Fusion A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System:A Way for Early Application of Fusion Technology Neutron

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Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER

Design analysis of the China dual-functional lithium lead (D...

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第十二届反应堆数值计算与粒子输运学术会议

作者： the FDS Team Institute of Plasma Physics Chinese Academy of Sciences

The dual-functional lithium lead-test blanket module (DFLL-TBM) system,which is designated to check and validate,the relevant technologies of both the helium-cooled lithium-lead blanket and the helium/lithium-lead dual-cooled blanket for the Chinese fusion DEMO reactor,has been proposed for testing in ITER referring to the relevant several conceptual designs of liquid lithium-lead breeder blankets developed in *** detailed description of the basic structure,cooling scheme and auxiliary systems for DFLL-TBM has been given in this paper.A series of preliminary performance analyses have been performod to validate the feasibility of the DFLL-TBM *** results show that TBM design can satisfy the material requirements and ITER safety design requirements.

关键词： ITER Test Blanket Module Liquid lithium-lead blanket

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Fusion-Based Hydrogen Production Reactor and Its Material Selection

Fusion-Based Hydrogen Production Reactor and Its Material Se...

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第十二届反应堆数值计算与粒子输运学术会议

作者： FDS Team Institute of Plasma Physics Chinese Academy of Sciences

The fusion-based hydrogen production reactor (named FDS-Ⅲ),one of the series of fusion system design concepts developed in China,is designated to exploit the fusion energy advanced application for the production of *** this paper,a conceptual design of FDS-Ⅲis presented,including the design of plasma core parameters,high temperature blanket,divertor and related auxiliary *** particular,an innovative high temperature blanket (named HTL) concept with the multilayer flow channel inserts (MFCIs) in the liquid metal LiPb channels and the Reduced Activation Ferritic/Martensitic (RAFM) steel as the structural material is proposed to achieve LiPb outlet temperature of about 1000℃for high efficient production of *** preliminary performance analyses have demonstrated the feasibility of the *** on the design and analyses,a selection of the materials for the FDS-Ⅲreactor and related auxiliary systems has been performed with indication of further R&D needs.

关键词： Hydrogen production fusion reactor high temperature blanket material selection

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Conceptual Design of China Fusion Power Plant FDS-Ⅱ

Conceptual Design of China Fusion Power Plant FDS-Ⅱ

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第十二届反应堆数值计算与粒子输运学术会议

作者： FDS Team Institute of Plasma Physics Chinese Academy of Sciences

As one of the series of fusion system design concepts developed in China,the fusion power plant FDS-Ⅱwas designated to exploit and evaluate potential attractiveness of fusion energy application for the generation of electricity on the basis of conservatively advanced plasma parameters,which can be limitedly extrapolated from the successful operation of *** options of specific liquid LiPb blanket concepts for FDS-Ⅱhave been proposed,*** He/LiPb Dual-cooled Lithium Lead (DLL) breeder blanket (～700℃coolant outlet temperature) and the He-cooled Quasi-Static Lithium Lead (SLL) breeder blanket (～450℃coolant outlet temperature) with the RAFM steel as the structural *** this paper,an overview of the FDS-Ⅱconceptual design is presented and a series of performance analyses are *** further R&D needs are specified.

关键词： Fusion power plant Conceptual design Liquid blanket LiPb breeder

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Design status and development strategy of China liquid lithium-lead blankets and related material technology

Design status and development strategy of China liquid lithi...

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第十二届反应堆数值计算与粒子输运学术会议

作者： FDS Team Institute of Plasma Physics Chinese Academy of Sciences

A series of fusion reactors (named FDS series) have been designed and assessed in China,with four types of liquid lithium lead blankets including the RAFM steel-structured He-cooled quasi-static LiPb tritium breeder (SLL) blanket, the RAFM steel-structured He-LiPb dual-cooled (DLL) blanket,the RAFM steel-structured refractory material thermally-insulated high temperature LiPb (HTL) hydrogen production blanket and the RAFM steel or optionally the austenitic stainless steel-structured He-LiPb dual-cooled high level waste transmutation (DWT) *** demonstrate and validate the feasibility of the candidate blankets for fusion energy application,the three-phases-strategy of TBM (test blanket module) development,*** R&D and out-of-pile experimental mockup,EAST-TBM and ITER-TBM have been proposed.A brief overview of the four types of LiPb blanket designs and their goals are *** technology requirement and development strategy are also presented in this paper.

关键词： DWT Design status and development strategy of China liquid lithium-lead blankets and related material technology

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The fusion-driven hybrid system and its material selection

The fusion-driven hybrid system and its material selection

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第十二届反应堆数值计算与粒子输运学术会议

作者： Y.C.Wu~(a,*) J.P.Qian~a J.N.Yu~b ~a Institute of Plasma Physics,Chinese Academy of Sciences,P.O.Box 1126,Hefei,Anhui 230031,China b China Institute of Atomic Energy,P.O.Box 275-51,Beijing 102413,China

The fusion-driven multi-functional hybrid reactor system (FDS) is proposed as a middle step toward the final ap- plication of fusion *** strategic goal and roadmap of the FDS is addressed along with its potential advantages. Selection analysis of required materials are performed as well as those of fusion driver concept,hybrid blanket concept for the FDS in China.

关键词： The fusion-driven hybrid system and its material selection

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中国液态锂铅包层材料研究进展

中国液态锂铅包层材料研究进展

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第十二届反应堆数值计算与粒子输运学术会议

作者：黄群英李春京李艳芬刘少军宋勇彭蕾章毛连朱志强高胜郭智慧王永亮吴宜灿周新贵万发荣单以银郁金南朱升云张品源杨建锋李合琴巨新室贺健夫长坂琢也大贯惣明 FDS团队中国科学院等离子体物理研究所国防科技大学北京科技大学中国科学院金属研究所中国原子能科学研究院西安交通大学合肥工业大学日本国立聚变研究所北海道大学工学部中国科学院等离子体物理研究所

液态锂铅包层是国际上普遍关注和最有发展潜力的聚变堆包层概念设计之一,而包层材料是液态锂铅包层的核心问题之一。目前,液态锂铅包层普遍选用低活化铁素体/马氏体钢(RAFM钢)作为结构材料,液态锂铅作为中子倍增剂及氚增殖剂。另外,部... 详细信息

液态锂铅包层是国际上普遍关注和最有发展潜力的聚变堆包层概念设计之一,而包层材料是液态锂铅包层的核心问题之一。目前,液态锂铅包层普遍选用低活化铁素体/马氏体钢(RAFM钢)作为结构材料,液态锂铅作为中子倍增剂及氚增殖剂。另外,部分设计采用了耐高温、电绝缘流道插件作为功能材料.以降低磁流体动力学效应及提高冷却剂出口温度(高于700℃)。为适应液态包层的发展需求.中国科学院等离子体物理研究所FDS团队联合国内外相关研究单位,进行了具有中国自主知识产权的中国低活化马氏体钢(CLAM钢)及液态锂铅包层功能材料研发.并开展了锂铅热对流及强迫对流回路的设计、研制及腐蚀实验研究,以研究液态金属锂铅的流动特性及其与结构和功能材料的相容性。同时建立了聚变堆材料数据库平台.为促进中国聚变堆液态包层及材料技术的研究和发展提供数据支持。

关键词：液态包层中国低活化马氏体钢锂铅回路

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

Progress in Compatibility Experiments on Lithium-Lead with C...

引用

第十二届反应堆数值计算与粒子输运学术会议

作者： FDS Team Institute of Plasma Physics Chinese Academy of Sciences

Liquid LiPb eutectic is one of the promising candidates of tritium breeder materials for fusion *** paper presents the progress in compatibility experiments with liquid LiPb achieved up to now in China for some candidate structural *** results show that CLAM steel showed good compatibility with flowing LiPb at 480℃with the velocity of 0.08m/s after 5000 hrs in DRAGON-I *** the other hand,after exposed in static LiPb at 700℃for 500 hrs in a SiC crucible,the W and Mo specimens suffered much more weight loss compared with Nb specimen,and a thin reaction zone was visible on the surface of all the three refractory metals;and the matrix of 310S suffered severe corrosion attack;Preliminary analysis on SiC_f/SiC composite specimens indicated that no penetration of LiPb and no formation of reaction results were observed on the surface with CVD SiC coating,and showed the stable and compatible characteristics with static LiPb at this temperature after 500hrs' *** study for much longer time corrosion experiment at elevated temperature will be carried out in the near future.

关键词： Lithium Lead Structural Materials Compatibility

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Conceptual design activities of FDS series fusion power plants in China

Conceptual design activities of FDS series fusion power plan...

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第十二届反应堆数值计算与粒子输运学术会议

作者： FDS Team Institute of Plasma Physics Chinese Academy of Sciences

A series of fusion power plants (named FDS series) have been designed and assessed for the examination of the feasibility and the safety,environmental and economical potential of fusion with emphasizing the blanket design optimization on neutronics, thermal-hydraulics,electro-magnetics,material,structural performance analyses in *** concepts have been developing, which are the fusion-driven subcritical system (FDS-I) with the goal of transmutation of the long-lived nuclear wastes and breeding of fissile nuclear fuels,the fusion power reactor (FDS-Ⅱ) with the goal of electricity generation,the fusion-based hydrogen production reactor (FDS-Ⅲ) and the spherical tokamak-based compact reactor (FDS-ST).Four types of blankets, including the He/LiPb dual-cooled high level waste transmutation (DWT) blanket,the He single-cooled LiPb tritium breeder (SLL) blanket and the He/LiPb dual-cooled (DLL) blanket,the high temperature liquid LiPb (HTL) blanket,and Test Blanket Modules (TBMs) and the testing strategy have been studied.R&D status on materials,design and analysis tools are also presented.

关键词： Fusion power plant Liquid lithium lead blanket Test Blanket Module Conceptual design

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