• 不 限
  • 期刊论文
  • 硕博论文
  • 会议论文
  • 报 纸
  • 英文论文
  2. 您的位置
  3. 首页
  4. 会议论文
  5. Design and R&D activities of fusion breeder blankets in China

Design and R&D activities of fusion breeder blankets in China

来源 :第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) | 被引量 : 0次 | 上传用户：saif108
【摘 要】
：
China has long been active in pushing forward the fusion energy development to the demonstration of electricity generation.Two experts meetings were organized in 2014 by Ministry of Science and Techno
【作 者】
：
Jie Yu Muyi Ni Jieqiong Jiang Chunjing Li Shaojun Liu Zhiqiang Zhu Qunying Huang Yican Wu 
【机 构】
：
Key Laboratory of Neutronics and Radiation Safety,Institute of Nuclear Energy Safety Technology,Chin
【出 处】
：
第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
【发表日期】
：
2016年3期
【关键词】
：
Fusion Blanket TBM Development Roadmap 
下载到本地 , 更方便阅读
下载此文 赞助VIP
声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架
论文部分内容阅读
　　China has long been active in pushing forward the fusion energy development to the demonstration of electricity generation.Two experts meetings were organized in 2014 by Ministry of Science and Technology(MOST)to seriously discuss the Chinas fusion roadmap in particular the design and construction of magnetic confinement fusion reactor beyond ITER.
其他文献
Numerical simulation of hydrostatic extrusion of pure tungsten
Hydrostatic extrusion(HE)is a proper process to fabricate pure tungsten,because the hydrostatic pressure can effectively improve the formability of materials.In this study,the HE process at elevated t
会议
Hydrostatic ExtrusionFEA SimulationTungstenElasto-Plastic
Design/manufacturing of W alloy with high performance for using as plasma-facing materials
W offers excellent compatibility with liquid metals,high thermal conductivity,low sputtering yield,high hardness/strength are thus appealing for many important high temperature applications such as pl
会议
W alloyplasma-facing materialsO impurity
Preparation and thermal shock characterization of yttrium doped tungsten-potassium alloy
Tungsten and tungsten-based alloys are important materials in lighting,electronics,military and fusion reactors due to their good thermal conductivity,high melting point,low erosion rate and low triti
会议
Potassium-doped tungstenYttriumPreparationThermal shock
Recent progress on development of SIMP steel for accelerator driven system with LBE as coolant
Accelerator driven system(ADS)was proposed for the treatment of spent nuclear fuel.In principal,it takes together the advantages of transmutation of spent nuclear fuel as well as the safety.However,ma
会议
SIMP steelADSStructural materialLBEIrradiation
Status of research & development for DEMO at QST rokkasho fusion institute
Under the Broader Approach(BA)Activities,which are research and development activities jointly implemented by Japan and EURATOM in support of the ITER Project and an early realization of fusion energy
会议
Broader Approach ActivitiesDEMOneutron source
ODS steels R&D for application to advanced nuclear systems
Materials development is essential for realization of advanced nuclear systems.Among the several candidate structural materials of the nuclear systems,oxide dispersion strengthened(ODS)steels,which ha
会议
high performance mechanismnano-particlesHR-TEMradiation tolerance
Reconstruction of Japanese fusion materials development program toward DEMO
Some documents were recently issued by Japanese governmental committees.Japanese DEMO development strategy is under reconstruction based on these documents.This paper presents the Japanese strategy fo
会议
fusion materialsDEMOV-alloySiC/SiCODS-S
Challenges and status of CLAM steel for advanced reactors
The advanced reactor systems,such as fusion reactor and lead cooled reactor,bring up great challenges to the service performance of structural materials.Great efforts are being devoted to the developm
会议
CLAM steelTBMFusionQualification
Response of a high-Cr ODS ferritic steel to irradiation with high-energy heavy ions
A recent study on irradiation response of an Al-free Ti-added 16Cr-ODS ferritic steel by high-energy heavy ions is presented.Specimens were irradiated with 58Ni,20Ne and 16O ions,respectively,with a k
会议
ODS ferritic steelRadiation damageHeavy ionMechanical property
Role of He and annealing on the radiation-hardening in an austenitic steel
In first wall materials 14 MeV neutron irradiation introduces the nuclear transmutation of helium and hydrogen,as well as large amount of radiation damages.The phenomena lead materials degradation wit
会议
He bubbleradiation-hardeningHe diffusionadditional hardening