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模拟含An^(4+)放射性石墨的SHS固化处理研究 被引量:2

SHS Technology for Immobilizing Simulated Radioactive Graphite Containing An^(4+)
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摘要 为研究含An4+放射性石墨的SHS固化处理能力,以C、Al和TiO2为原料,CeO2为An4+模拟物质,利用自行设计的SHS反应装置模拟开展含An4+放射性石墨的固化研究。借助X射线衍射仪对所制备固化体的物相、相关系及固溶度等进行研究,并对样品的XRD数据进行了结构精修。结果表明:在空气气氛中,利用3C+4Al+3TiO2=2Al2O3+3TiC反应进行含An4+放射性废物的SHS固化处理,其固溶度为3%(以质量计,下同)。固溶度为0%~3%的固化体以Al2O3、TiC、C、TiO2和AlN相存在,燃烧产物中Al2O3的晶胞参数a、b和c发生了10-3nm量级变化,V发生了10-3nm3量级变化,α、β和γ发生了(10-3)°~(10-1)°量级变化;产物中TiC的晶胞参数a、b和c发生了10-3nm量级变化,V发生了10-3nm3量级变化,α、β和γ未出现变化。所制备的样品形貌不规则,主要以块状为主,晶粒度主要集中在5~20μm之间。 In order to develop SHS technology for immobilizing radioactive graphite containing An^4+,CeO2 was used as the simulacrums for An^4+,the waste forms were synthesized by designed equipment and using C,Al and TiO2 powders as the starting materials.The phase,solubility of An^4+ and the relationship of phases in waste forms were analyzed by the help of X-ray diffraction(XRD) instrument.Moreover,the crystal cell parameters were calculated by structural refinement method.The results indicate that the solubility of simulacrum in waste forms is 3%(in weight)treating the radioactive wastes containing An^4+ by the reaction: 3C+4Al+3TiO2 = 2Al2O3+3TiC.The waste forms exist as Al2O3,TiC,C,TiO2 and AlN phase when the contents of CeO2 in the range of solubility.Crystal cell parameters a,b and c in Al2O3 crystal lattices change about 10-3 nm magnitude,the value of V varies about 10-3 nm^3 magnitude,and α,β and γ change from(10^-3)° to(10^-1)° magnitude.The crystal cell parameters a,b,c of TiC in combustion products vary about 10-3nm magnitude,and the volume of crystal cell changes about 10-3 nm^3 magnitude,and α,β and γ are not found changes.The as-gained samples were mostly block-shaped and grain sizes distribute mainly in a range of 5~20 μm.
出处 《武汉理工大学学报》 CAS CSCD 北大核心 2012年第7期18-22,共5页 Journal of Wuhan University of Technology
基金 国家自然科学基金(21007052) 四川大学辐射物理及技术教育部重点实验室基金(2011-03) 西南科技大学核废物与环境安全国防重点学科实验室基金(11zxnk09)
关键词 SHS 放射性废物 固化体 固溶度 SHS radioactive waste waste forms solubility
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参考文献14

  • 1Wiley J B,Kaner R B.Rapid Solid-state Precursor Synthesis of Materials[J].Science,1992,255(5048):1093-1097.
  • 2Moore J J,Feng H J.Combustion Synthesis of Advanced Materials:Classification,Applications and Modeling[J].ProgMater Sci,1995,39(4-5):275-316.
  • 3Orru R,Sannia M,Cincotti A,et al.Treatment and Recycling of Zinc Hydrometallurgical Wastes by Self-propagatingReactions[J].Chem Eng Sci,1999,54(15-16):3053-3061.
  • 4Muthuraman M,Aruldhas N,Patil K C.Combustion Synthesis of Oxide Materials for Nuclear Waste Immobilization[J].Bull Mater Sci,1994,17(6):977.
  • 5Vinokurov S E,Kulyako Y M,Perevalov S A,et al.Immobilization of Actinides in Pyrochlore-type Matrices Producedby Self-propagating High-temperature Synthesis[J].C R Chimie,2007,10:1128-1130.
  • 6Yudintsev S V,Ioudintseva T S,Mokhov A V,et al.Study of Pyrochlore and Garnet-based Matrices for Actinide WasteProduced by a Self-propagating High-temperature Synthesis[J].Materials Research Society,2004,807:1-6.
  • 7Merzhanov A G,Stolin A M,Podlesov V V.SHS Extrusion of Long Sized Articales from Metalloceramic Materials[J].Ceramic Sci,1997,17:447.
  • 8Mochida T J,Yamashita J.Transmutation of Long-lived Fission Products with Use of Available Excess Neutrons inBWR Core[J].Process in Nuclear Energy,1998,32(3/4):579.
  • 9Borovinskaya I P,Barinova T V,Ratnikov V I,et al.Consolidation of Radioactives Waste into Mineral Like Material bythe SHS Method[J].Inter J SHS,1998,7(1):129.
  • 10]Barinova T V,Borovinskaya I P,Atnikov V I R,et al.SHS Immobilization of Radioactive Wastes[J].Kay EngineeringMaterials,2002,217:193.

二级参考文献39

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同被引文献12

  • 1International Atomic Energy Agency (IAEA). Character- ization, Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors[ C ]. VIENNA : IAEA in Austria ; 2006.
  • 2FACHINGER J, LENSA W V, PODRUHZINA T. De- contamination of nuclear graphite [ J ]. Nuclear Engineer- ing and Design, 2008, 238 : 3086 -3091.
  • 3MUTHURAMAN M, ARULDHAS N, PATIL K C. Com- bustion synthesis of oxide materials for nuclear waste im- mobilization[J]. Bull. Mater. Sci., 1994, 17:977.
  • 4VINOKUROV S E, KULYAKO Y M, PEREVALOV S A, et al. Immobilization of actinides in pyrochlore - type matrices produced by self - propagating high - tempera- ture synthesis[J]. C. R. Chimie, 2007,10:1128-113.
  • 5YUDINTSEV S V, IOUDINTSEVA T S, MOKHOV A V, et al. Study of pyrochlore and garnet - based matrices for Actinide waste produced by a self- propagating high - temperature synthesis [ J ]. Materials Research Society, 2004, 807 : 1 - 6.
  • 6MERZHANOV A G, STOLIN A M, PODLESOV V V. SHS extrusion of long sized articales from metalloceramic materials[J]. Ceramic Sci., 1997, 17: 447.
  • 7MOCHIDA T J, YAMASHITA J. Transmutation of long - lived fission products with use of available excess neu- trons in BWR core [ J ]. Process in Nuclear Energy, 1998, 32:579.
  • 8BOROVINSKAYA I P, BARINOVA TV, RATNIKOVV I, et al. Consolidation of radioactives waste into mineral like material by the SHS method [ J]. Inter. J. SHS, 1998, (7) :129.
  • 9BARINOVA TV, BOROVINSKAYA I P, ATNIKOVV IR, et al. SHS Immobilization of radioactive wastes [ J ]. Kay Engineering Materials, 2002, 217 : 193.
  • 10张瑞珠,赵军华,郭志猛.二次自蔓延高温合成SrTiO3固化高放废物[J].稀有金属,2009,33(1):66-70. 被引量:7

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