期刊文献+

聚变-裂变混合堆液态锂铅包层中氚提取系统设计 被引量:2

Primary Design of a Tritium Extraction System of the Liquid Lithium-Lead Blanket for the Fusion-Fission Hybrid Reactor
下载PDF
导出
摘要 液态锂铅合金是很有前途的聚变-裂变混合堆(FFHR)产氚包层增殖材料。作为聚变-裂变混合堆中最重要的辅助单元,液态锂铅包层氚提取系统(LLLB-TES)通过含0.1%H2的低压氦吹洗气流,将产氚包层中产生的氚交换和载带出来,进入同位素分离系统中连续进行氚的提取,实现混合堆氘氚核燃料的循环。为了完成这一挑战性工程的前期概念设计,本文给出了该系统总体参数、工艺流程、辅助设施等方面的描述,将TES划分为锂铅鼓泡、吹洗气配制、氢同位素色谱分离和氚贮存4个回路,凸现工程化的应用前景。 The liquid lithium lead alloy is a prominent breeder material for the Fusion-Fission Hybrid Reactor (FFHR) tritium blanket. The Tritium Extraction System of the Liquid Lithium-Lead Blanket (LLLB-TES) is one of the most important ancillary units in FFHR. In our design, in order to realize the D-T fuel circulation, the main function of the LLLB-TES is to extract tritium produced in liquid LiPb blanket by purge gas, to control the gas composition of the low pressure purge flow and to provide tritium-breeding data of liquid LiPb loop by measuring and monitoring operation parameters of the system (temperature, pressure, gas Components, gas flow rates, tritium concentration, etc.), and to test the reliability of TES. This paper reviews the state-of-the-art of the T related technology from the initial T production in the LiPb breeder material to a T stream which is ready for re-injection into the plasma. The development issues are outlined and conventional techniques are compared with advanced methods which require more R&D effort but promise advantages in return. System parameters, flow process, analytical instrument and ancillary installations are discussed in detail.
出处 《科技导报》 CAS CSCD 2008年第23期23-26,共4页 Science & Technology Review
基金 中国工程物理研究院ITER专项基金项目(20060205540)
关键词 氚提取 锂铅合金 混合堆 tritium extraction LiPb alloy hybrid reactor
  • 相关文献

参考文献7

  • 1黄群英,陈明亮,彭蕾,朱晓翔,陈义学,吴宜灿.聚变驱动次临界堆双冷嬗变包层材料活化计算与分析[J].核科学与工程,2004,24(3):269-276. 被引量:5
  • 2Futterer M A, Bielak B, Deffain J P, et al. Design development and manufacturing sequence of the European water-cooled Pb-17Li test blanket module [J]. Fusion Engineering and Design, 1998, 39-40: 851- 858.
  • 3Futterer M A, Albrecht H, Giroux P, et al. Tritium technology for blankets of fusion power plants [J]. Fusion Engineering and Design, 2000, 49-50: 735-743.
  • 4Xie Bo, Weng Kuiping, Liu Yunnu. Theoretical calculation of tritium extraction from liquid LiPb by bubble columns [J]. Nuclear Science and Technology Applications, 2007, 3(1): 47-50.
  • 5Iwai Y, Misaki Y, Hayashi T, et ol. The water detritiation system of the ITER tritium plant [J]. Fusion Science and Technology, 2002, 41 (2): 1126-1130.
  • 6Dworschak H, Malara C, Ricapito I, et al. Comparative analysis of tritium recovery methods from Pb-17Li water-cooled blanket [J]. Fusion Technology, 1995, 28(1): 578-585.
  • 7谢波,刘云怒,翁葵平,侯建平,官锐.色谱柱程序升温脱附法分离氢同位素[J].科技导报,2007,25(20):33-35. 被引量:6

二级参考文献21

共引文献9

同被引文献25

引证文献2

二级引证文献5

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部