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R&D activities of the liquid breeder blanket in Korea

机译:韩国液体育种毯的研发活动

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摘要

A liquid breeder blanket has been developed in parallel with the International Thermonuclear Experimental Reactor (ITER) Test Blanket Module (TBM) program in Korea. The Korea Atomic Energy Research Institute (KAERI) has developed the common fields of a solid TBM such as design tools, structural material, fabrication methods, and He cooling technology to support this concept for the ITER. Also, other fields such as a liquid breeder technology and tritium extraction have been developed from the designed liquid TBM. For design tools, system codes for safety analysis such as Multi-dimensional Analysis of Reactor Safety (MARS) and GAs Multi-component Mixture Analysis (GAMMA) were developed for He coolant and liquid breeder. For the fabrication methods, Ferritic Martensitic Steel (FMS) to FMS and Be to FMS joinings with a Hot Isostatic Pressing (HIP) were developed and verified with a high heat flux test of up to 0.5-1.0 MW/m2. Moreover, three mockups were successfully fabricated and a 10-channel prototype is being fabricated to make a rectangular channel FW. For the integrity of the joining, two high heat flux test facilities were constructed, and one using an electron beam has been constructed. With the 6 MPa nitrogen loop, a basic heat transfer experiment for code validation was performed. From the verification of the components such as preheater and circulator, a 9 MPa He loop was constructed, and it supplies high temperature (500 C) and pressure (8 MPa) He to the high heat flux test facility. For an electromagnetic (EM) pump development for circulating the liquid breeder, magneto-hydrodynamic (MHD) experiment, and flow corrosion test, a PbLi breeder loop was constructed. From the performance test, the EM pump and magnet show their capability, and flow and static corrosion tests including oxide coating for corrosion protection were performed. For tritium extraction from the liquid breeder, a gas-liquid contact method was adopted and a tritium extraction chamber was constructed. For measurement of the tritium amount in the liquid breeder, permeation sensors have been developed.
机译:在韩国与国际热核实验堆(ITER)测试毯模块(TBM)计划同时开发了液体育种毯。韩国原子能研究所(KAERI)已开发出固体TBM的通用领域,例如设计工具,结构材料,制造方法和氦冷却技术,以支持ITER的这一概念。另外,从设计的液体TBM中发展了液体育种技术和tri提取等其他领域。对于设计工具,针对氦冷却剂和液体育种人员开发了用于安全分析的系统代码,例如反应堆安全性的多维分析(MARS)和GA多组分混合物分析(GAMMA)。对于制造方法,开发了具有热等静压(HIP)的铁素体马氏体钢(FMS)到FMS和Be到FMS接头,并通过了高达0.5-1.0 MW / m2的高热通量测试进行了验证。此外,成功制作了三个模型,并制作了一个10通道的原型以制作矩形通道FW。为了保证连接的完整性,建造了两个高热通量测试设备,其中一个使用了电子束。使用6 MPa的氮气回路,进行了用于代码验证的基本传热实验。通过对预热器和循环器等组件的验证,构建了一个9 MPa的He回路,该回路为高热通量测试设备提供了高温(500 C)和压力(8 MPa)He。为了开发用于循环液体繁殖器的电磁(EM)泵,磁流体动力学(MHD)实验和流腐蚀测试,构建了PbLi繁殖器回路。从性能测试中,EM泵和磁铁显示出它们的性能,并进行了流动和静态腐蚀测试,包括用于腐蚀防护的氧化物涂层。为了从液体育种者中提取tri,采用气-液接触法并构造了extraction提取室。为了测量液体育种器中的amount含量,已经开发了渗透传感器。

著录项

  • 来源
    《Fusion Engineering and Design》 |2012年第6期|p.706-711|共6页
  • 作者单位

    Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    National Fusion Research Institute, Daejeon, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    ITER; TBM; liquid breeder; breeding blanket;

    机译:ITER;太;液体饲养员繁殖毯;

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