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热循环吸附法分离氕、氘的研究 被引量:4

Separation of Protium-Deuterium by Thermal Cycling Absorption Process
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摘要 对热循环吸附法(TCAP)全回流模式和生产模式下的氕-氘分离实验进行了研究。全回流模式下,主要考核了初始进料比、冷/热循环温度、进料位置对分离效果的影响。结果表明,原料气体从分离柱中部进料时,初始进料比相对越大,冷/热循环温差越大,分离效果越好;而从回流柱进料时,分离效果相对更好。在几组实验中,回流柱初始进料为90%、冷/热循环温度分别为56℃/290℃的一组效果最好。生产模式下,由于分离柱中气阻较大,有可能影响氕、氘的分离效果,这部分实验还有待继续进行。 Thermal cycling absorption process (TCAP), a semi-continuous hydrogen isotope separation process, is of many unique advantages. TCAP system designed in this work mainly consists of a separation column, feeding and withdrawing subsystem, column cooling and heating subsystem, data collection and autocontrol subsystem. About 901 g Pd/K was packed in the column. The palladium mass content of the Pd/K whose particle sizes were 250-400μm was about 40. 8%. The hydrogen absorption capacity of the column was 27. 016 L(STP). The system was tested in total reflux mode at different operation parameters including initial feeding ratio, cooling or heating temperatures, feeding place of raw gases in order to confirm the best operation conditions of hydrogen isotope separation. The results show that the higher initial feeding ratio the better the separation effects will be when and temperature difference of the column are, feeding at the midpoint of the column. If the gases are fed from the plug-flow reverser (PFR), the separation results will be better. The best one among the experiments is the one that fed 90 % into the column from the PFR with cooling at 56 ℃ and heating at 290 ℃. The deuterium content in the product reaches 99.2% after 30 cycles. The protium contents in the raffinate and separation factor are 96. 1% and 3 055.49 respectively after 60 cycles. Separation of protium-deuterium was also done in online mode with the parameters of initial feeding of 90%, feeding and withdrawing of 3% during separation, cooling the column at 21 ℃ and heating at 290 ℃ in order to validate the separation capacity of TCAP. The results are not good because of the large gas resistance in the column, which may be induced from two aspects as Pd/K pulverization and jam of the column joint. So there are still some problems need to be solved in the construction of a TCAP facility and the hydrogen isotope separation in on-line mode.
出处 《核化学与放射化学》 EI CAS CSCD 北大核心 2007年第2期65-70,共6页 Journal of Nuclear and Radiochemistry
关键词 TCAP 氢同位素 分离 全回流模式 生产模式 TCAP hydrogen isotope separation total reflux mode on-line mode
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参考文献7

  • 1Horen A S,Lee M W.Metal Hydride Based Isotope Separation Large-Scale Operations[J].Fusion Technology,1992,21:282-286.
  • 2Ducret D,Laquerbe C,Ballanger A,et al.Separation of Hydrogen Isotopes by Thermal Cycling Absorption Process:an Experimental Evice[J].Fusion Sci Technol,2002,41:1 092-1 096.
  • 3Lu Guangda,Jiang Guoqiang,Shen Cansheng.An Experiment Investigation for Hydrogen and Deuterium Separation by Thermal Cycling Absorption Process[J].Fusion Sci Technol,1995,28:672-675.
  • 4Ortman M S,Heung L K,Nobile A,et al.Tritium Processing at the Savannah River Site (SRS)-Present and Future,WSRC-RP-89-65[R].Boston:WSRC,1989.
  • 5杨柯,宋莉,吕曼祺.贮氢材料在氚技术中的应用[J].原子能科学技术,2004,38(4):328-333. 被引量:14
  • 6Lee M W.Tritium Separation Using Metal Hydrides,DP-MS-86-11[R].Oxnard,California:SRL,1986.
  • 7Klein J E,Heung L K,Howard D W,et al.Conceptual Design for Consolidation TCAP,WSRC-TR-97-00340[R].Westinghouse Savannah River Company:Savannah River Technology Center,1997.

二级参考文献27

  • 1Nasise E. Performance and Improvement of the Tritium Handling Facility at the Los-Alamos Laboratory[J]. Inter J Applied Radiat Isot, 1980, 31(8):491~497.
  • 2Carstens DHW, David WR. Metal-hydrogen Systems[M]. New York:Pergamon-Elsvier,1978.378.
  • 3Ortman MS, Heung LK, Noible A, et al. Tritium Processing at the Savannah River Site-precent and Future[J]. J Vac Sci Technol, 1990, A8:2 881~2 889.
  • 4Thibaut S. Structural Changes in Pd (Ru,Pt) Solid Solution Due to He-3 Formation During Tritium Storage[J]. Phys Rev B, 1998, 57(10):10 379~10 387.
  • 5Weaver HT, William JC. Detrapping of Inter-stial Helium in Metal Tritides-NMR Stadies[J]. Phys Rev B, 1975, 12:3 054~3 059.
  • 6Bowman RC, Attalla A. NMR Stadies of Helium Distribution in Uranium Tritide[J]. Phys Rev B, 1977, 16:1 828~1 843.
  • 7Bowman RC. Helium Distribution in Metal Tri-tide[J]. Nature, 1978, 271:531~533.
  • 8Mitchell DJ. Temperature a-dependance of Helium Release From Erbium Tritide Films[J]. J Vac Sci Technol, 1981, 19:236~242.
  • 9Vedeneev AI. Radiagenic Helium Thermodesorption from Titainium Tritide[J]. J Nucl Mater, 1996, 233:1 189~1 192.
  • 10Emig JA, Garza RG, Christernsen LD, et al. Helium Release From 19-year-old Palladium Tritide[J]. Nucl, 1992, 187:209~214.

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