硅酸盐学报

参考文献

[1]顾忠茂,柴之芳.关于我国核燃料后处理/再循环的一些思考[J].化学进展,2011,23(7):1263-1271.GU Zhongmao,CHAI Zhifang.Prog in Chem (in Chinese),2011,23(7):1263-1271.

[2]孙亚平.熔盐堆含氟放射性废物磷酸盐固化方案及固化体性能研究[D].上海:中国科学院研究生院(上海应用物理研究所),2016.SUN Yaping.Study on phosphate solidification scheme and solidified properties of fluorinated fluoroethylene waste in molten salt reactor (in Chinese,dissertation),Shanghai:Shanghai Institute of Applied Physics,Chinese Academy of Sciences,2016.

[3]王承遇,陶瑛.玻璃材料手册[M].北京:化学工业出版社,2007:736-742.

[4]OJOVAN M,BATYUKHNOVA O.Glasses for nuclear waste immobilization[C]//WM2007 Conference,Tucson,AZ,United States,2007.

[5]OJOVAN M I,LEE W E.Glassy waste forms for nuclear waste immobilization[J].Metall Mater Transact A,2011,42(4):837-851.

[6]OJOVAN M I,LEE W E,KALMYKOV S N.An Introduction to Nuclear Waste Immobilisation[M].3rd ed.Elsevier,2019:319-368.

[7]JANTZEN C M.Systems approach to nuclear waste glass development[J].J Non-Cryst Solids,1986,84(1-3):215-225.

[8]干福熹.现代玻璃科学技术(上册)[M].上海:上海科学技术出版社,1988.

[9]PIOVESAN V,BARDEZGIBOIRE I,FOURNIER M,et al.Chemical durability of peraluminous glasses for nuclear waste conditioning[J].npj Mater Degrad,2018,2(1):1-10.

[10]LU X,DENG L,KERISIT S,et al.Structural role of Zr O2 and its impact on properties of boroaluminosilicate nuclear waste glasses[J].npj Mater Degrad,2018,2(19):1-10.

[11]GO?T T L,HARRISON M T,FARNAN I.Impacts of lithium on Magnox waste glass dissolution[J].J Non-Cryst Solids,2019,517:96-105.

[12]张华,HYATT N C,STEVENS J R,等.Zn O和Ca O对模拟高放废液硅酸盐玻璃固化体性能的影响研究[J].原子能科学技术,2015,49(7):1159-1164.ZHANG Hua,HYATT N C,STEVENS J R,et al.Atom Energy Sci Technol (in Chinese),2015,49(7):1159-1164.

[13]HOPF J,KERISIT S N,ANGELI F,et al.Glass-water interaction:Effect of high-valence cations on glass structure and chemical durability[J].Geochim Cosmochim Acta,2016,181:54-71.

[14]赵彦钊,殷海荣.玻璃工艺学[M].北京:化学工业出版社,2006.

[15]SOBOLEV I,DMITRIEV S,LIFANOV F,et al.A History of vitrification process development at sia radon including cold crucible melters[C]//WM2004 Conference,Tucson,AZ,United States,2004.

[16]CHAUVIN E,MAHUT P,TRONCHE E,et al.La Hague continuous improvement program to go beyond the current high level of equipment availability of the vitrification facility:Operation support with specific numerical tools[C]//WM2010 Conference,Phoenix,AZ,United States,2010.

[17]PETITJEAN V,DE VERA R,HOLLEBECQUE J,et al.La Hague continuous improvement program:Enhancement of the vitrification throughput[C]//WM2006 Conference,Tucson,AZ,United States,2006.

[18]KAMIZONO H,NIWA K.An estimation of the thermal shock resistance of simulated nuclear waste glass under water quenching conditions[J].J Mater Sci Lett,1984,3:588-590.

[19]BARTH N,GEORGE D,AHZI S,et al.Modeling and simulation of the cooling process of borosilicate glass[J].J Eng Mater Technol,2012,134(4):041001.

[20]DUBéM,DOQUET V,CONSTANTINESCU A,et al.Modeling of thermal shock-induced damage in a borosilicate glass[J].Mech Mater,2010,42(9):863-872.

[21]LUTZE W,BORCHARDT J,DéA K.Characterization of glass and glass ceramic nuclear waste forms[C]//MCCARTHY G J ed.Scientific Basis for Nuclear Waste Management.New York:Plenum Press,1979:69-81.

[22]KARAKURT G,ABDELOUAS A,GUIN J P,et al.Understanding of the mechanical and structural changes induced by alpha particles and heavy ions in the French simulated nuclear waste glass[J].J Nucl Mater,2016,475:243-254.

[23]PEUGET S,CACHIA J N,JéGOU C,et al.Irradiation stability of R7T7-type borosilicate glass[J].J Nucl Mater,2006,354(1-3):1-13.

[24]GIN S,JOLLIVET P,TRIBET M,et al.Radionuclides containment in nuclear glasses:An overview[J].Radiochim Acta,2017,105(11):927-959.

[25]WEBER W J,EWING R C,ANGELL C A,et al.Radiation effects in glasses used for immobilization of high-level waste and plutonium disposition[J].J Mater Res,1997,12(8):1948-1978.

[26]王铁山,张多飞,陈亮,等.辐照导致硼硅酸盐玻璃机械性能变化[J].物理学报,2017,66(2):26101.WANG Tieshan,ZHANG Duofei,CHEN Liang,et al.Acta Phys Sin(in Chinese),2017,66(2):026101.

[27]MALKOVSKY V I,YUDINTSEV S V,OJOVAN M I,et al.The influence of radiation on confinement properties of nuclear waste glasses[J].Sci Technol Nucl Install,2020(3):1-14.

[28]JIANG N,SILCOX J.High-energy electron irradiation and Bcoordination in Na2O-B2O3-Si O2 glass[J].J Non-Cryst Solids,2004,342(1-3):12-17.

[29]SUN K,WANG L,EWING R C,et al.Effects of electron irradiation in nuclear waste glasses[J].Philos Mag,2005,85(4-7):597-608.

[30]OLLIER N,CHAMPAGNON B,BOIZOT B,et al.Influence of externalβ-irradiation in oxide glasses[J].J Non-Cryst Solids,2003,323(1-3):200-206.

[31]OJOVAN M I.Handbook of Advanced Radioactive Waste Conditioning Technologies[M].Cambridge:Woodhead Publishing Limited,2011.

[32]JANTZEN C M.First principles process-product models for vitrification of nuclear waste:Relationship of glass composition to glass viscosity,resistivity,liquidus temperature,and durability[C]//93rd Annual Meeting of the American Ceramic Society,Ohio,United States,1991:1-20.

[33]JANTZEN C M.Method for melting glass by measurement of non-bridging oxygen[P].US Patent,5102439,1992.

[34]CAROL J.The impacts of uranium and thorium on the defense waste processing facility (DWPF) viscosity model[R].WSRC-TR-2004-00311,Aiken,SC:Savannah River Lab,2005.

[35]FULCHER G.Analysis of recent measurements of the viscosity of glasses-Ⅱ[J].J Am Ceram Soc,1925,8(12):789-794.

[36]FULCHER G S.Analysis of recent measurements of the viscosity of glasses[J].J Am Ceram Soc,1925,8(6):339-355.

[37]SCHERER G W.Editorial comments on a paper by Gordon S.Fulcher[J].J Am Ceram Soc,1992,75(5):1060-1062.

[38]MAURO J C,TANDIA A,VARGHEESE K D,et al.Accelerating the design of functional glasses through modeling[J].Chem Mater,2016,28:4267-4277.

[39]BACH H,BAUCKE F G K,KRAUSE D.Electrochemistry of Glasses and Glass Melts,Including Glass Electrodes[M].New York:Springer-Verlag Berlin Heidelberg,2001.

[40]FANG X,RAY C S,MARASINGHE G K,et al.Properties of mixed Na2O and K2O iron phosphate glasses[J].J Non-Cryst Solids,2000,263-264:293-298.

[41]VAUGHAN J G,KINSER D L.Electrical resistivity surface for Fe O-Fe2O3-P2O5 glasses[J].J Am Ceram Soc,1975,58(7/8):326-329.

[42]BICKFORD D F,PROPST R,PLODINEC M.Control of radioactive waste-glass melters:Part 3,Glass electrical stability[R].DP-MS-88-14,Aiken,SC:Savannah River Lab,1988.

[43]YOSHIOKA M,TORATA S,IGARASHI J,et al.Glass melter and process development for PNC Tokai vitrification facility[J].Waste Manage,1992,12(1):7-16.

[44]IGARASHI H,KAWAMURA K,TAKAHASHI T.Effects of noble metal elements on viscosity and electrical resistivity of simulated vitrified products for high-level liquid waste[J].MRS Online Proceedings Library (OPL),1991,257:169-176.

[45]田英良,孙诗兵.新编玻璃工艺学[M].北京:中国轻工业出版社,2009.

[46]RILEY B J,HRMA P R,VIENNA J D,et al.The liquidus temperature of nuclear waste glasses:An international round-robin study[J].Int JAppl Glass Sci,2011,2(4):321-333.

[47]ASTM.ASTM C1720-17 Standard Test Method for Determining Liquidus Temperature of Immobilized Waste Glasses and Simulated Waste Glasses[S].ASTM International.West Conshohocken,2017.

[48]VIENNA J D,FLUEGEL A,KIM D S,et al.Glass property data and models for estimating high-level waste glass volume[R].PNNL-18501,Richland,Washington:Pacific Northwest National Laboratory (PNNL),2009.

[49]PIEPEL G,VIENNA J,CRUM J,et al.Liquidus temperature data for DWPF glass[R].PNNL-11790,Richland,Washington:Pacific Northwest National Laboratory (PNNL),1999.

[50]MIKA M,SCHWEIGER M J,VIENNA J D,et al.Liquidus temperature of spinel precipitating high-level waste glasses[J].MRSOnline Proceedings Library (OPL),1996,465:71-78.

[51]MARRA S,JANTZEN C.Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling[R].WSRC-TR-92-142,Aiken,SC:Westinghouse Savannah River Co.,1993.

[52]CHRISTIAN J.Examining the role of canister cooling conditions on the formation of nepheline from nuclear waste glasses[R].SRNL-STI-2015-00429,Aiken,SC:Savannah River Site (SRS),2015.

[53]LI H,VIENNA J D,HRMA P,et al.Nepheline precipitation in high-level waste glasses:Compositional effects and impact on the waste form acceptability[J].Mater Res Soc Symposia Proc,1996,465:261-268.

[54]KESTERSON M R.COMSOL Multiphysics model for HLW canister filling[R].SRNL-STI-2015-00207,Aiken,SC:Savannah River Site(SRS),2016.

[55]VERNAZ E.Nuclear Waste Conditioning[M].France:CEA,2009.

[56]MURRAY P,BAILLY F,STRACHAN D,et al.Qualification of a vitrified high level waste product to support used nuclear fuel recycling in the US-9474[C]//WM2009 Conference,Phoenix,AZ,2009.

[57]KAUSHIK C,MISHRA R,SENGUPTA P,et al.Barium borosilicate glass--A potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste[J].J Nucl Mater,2006,358(2/3):129-138.

[58]刘丽君,李金英,赵屹东,等.硼硅酸盐玻璃中硫的形态和结构的XANES方法研究[J].原子能科学技术,2008,42(Sl):49-52.LIU Lijun,LI Jinying,ZHAO Yidong,et al.Atom Energy Sci Technol(in Chinese),2008,42(Sl):49-52.

[59]刘丽君,郄东生,周慧,等.高硫高钠高放废液玻璃固化的配方验证[J].核化学与放射化学,2014,36(3):163-168.LIU Lijun,QIE Dongsheng,ZHOU Hui,et al.J Nucl Radiochem (in Chinese),2014,36(3):163-168.

[60]MISHRA R K,SUDARSAN K V,SENGUPTA P,et al.Role of sulfate in structural modifications of sodium barium borosilicate glasses developed for nuclear waste immobilization[J].J Am Ceram Soc,2008,91(12):3903-3907.

[61]MOGHISSI A A.Radioactive waste forms for the future[J].Waste Manage,1990,10(1):79-79.

[62]SHORT R,HAND R,HYATT N,et al.Environment and oxidation state of molybdenum in simulated high level nuclear waste glass compositions[J].J Nucl Mater,2005,340:179-186.

[63]SHORT R,HAND R,HYATT N.Molybdenum in nuclear waste glasses-incorporation and redox state[J].MRS Online Proceedings Library (OPL),2002,757:II5.4.

[64]PEGG I L,GAN H,MATLACK K S,et al.Mitigation of yellow phase formation at the Rokkasho HLW vitrification facility-10107[C]//WM2010 Conference,Phoenix,AZ,2010.

[65]GAN H,MATLACK K S,PEGG I L,et al.Suppression of yellow phase formation during Japanese HLW vitrification[C]//DOGAN F,TRITT T M,SEKINO T,et al.Ceramics for Environmental and Energy Applications II:Ceramic Transactions,John Wiley&Sons,Inc.,2014,246:237-250.

[66]谭盛恒,HAND R J.钼酸盐在硼硅酸盐玻璃体系中的溶解[J].中国材料进展,2016,35(7):496-503.TAN Shengheng,HAND R J.Mater Chin (in Chinese),2016,35(7):496-503.

[67]HRMA P,POKORNY R,LEE S M,et al.Heat transfer from glass melt to cold cap:Melting rate correlation equation[J].Int J Appl Glass Sci,2019,10:143-150.

[68]HRMA P.Melting of foaming batches:Nuclear waste glass[R].PNL-SA 18408,Richland,Washington:Pacific Northwest Lab,1990.

[69]PIERCE D A,HRMA P,MARCIAL J,et al.Effect of alumina source on the rate of melting demonstrated with nuclear waste glass batch[J].Int J Appl Glass Sci,2012,3(1):59-68.

[70]POKORNY R,HRMA P R.Model for the conversion of nuclear waste melter feed to glass[J].J Nucl Mater,2014,445(1-3):190-199.

[71]LEE S M,HRMA P,POKORNY R,et al.Glass production rate in electric furnaces for radioactive waste vitrification[J].J Am Ceram Soc,2019,102(10):5828-5842.

[72]LEE S M,FERKL P,POKORNY R,et al.Simplified melting rate correlation for radioactive waste vitrification in electric furnaces[J].JAm Ceram Soc,2020,103(10):5573-5578.

[73]MOTYKA T.Technical data summary for in-tank sludge processing[R].US DOE Report DPSTD-84-100,Aiken,SC:EI Du Pont de Nemours&Co.,Savannah River Laboratory,1984.

[74]RAPKO B M,LUMETTA G J.Status report on phase identification in Hanford tank sludges[R].PNNL-13394,Richland,Washington:Pacific Northwest National Laboratory,2000.

[75]KEEFER M,HAMM B,PIKE J.Low temperature aluminum dissolution of sludge waste[C]//WM2008 Conference,Phoenix,AZ,2008.

[76]盛嘉伟,罗上庚,汤宝龙.高放废液的玻璃固化及固化体的浸出行为与发展情况[J].硅酸盐学报,1997,25(1):83-88.SHENG Jiawei,LUO Shanggeng,TANG Baolong.J Chin Ceram Soc,1997,25(1):83-88.

[77]褚浩然,阮佳晟,张禹.高放玻璃固化体化学耐久性评估方法研究进展[J].山东化工,2017,46(16):65-70.CHU Haoran,RUAN Jiasheng,ZHANG Yu.Shandong Chem Ind (in Chinese),2017,46(16):65-70.

[78]张华.高放固化体处置条件下的浸出和模型研究[D].北京:中国原子能科学研究院,2004.ZHANG Hua.Study on leaching behavior and model of HLW-glass under repository conditions (in Chinese,dissertation).Beijing:China Institute of Atomic Energy,2004.

[79]张华,罗上庚.高放废物玻璃固化体浸出行为模型研究概况[J].辐射防护,2004,24(5):331-337.ZHANG Hua,LUO Shanggeng.Radiat Protect (in Chinese),2004,24(5):331-337.

[80]罗上庚.玻璃固化国际现状及发展前景[J].硅酸盐通报,2003,22(1):42-48.LUO Shanggeng.Bull Chin Ceram Soc(in Chinese),2003,22(1):42-48.

[81]FOURNIER M,GIN S,FRUGIER P.Resumption of nuclear glass alteration:State of the art[J].J Nucl Mater,2014,448(1):348-363.

[82]VERNAZ E,GIN S,JéGOU C,et al.Present understanding of R7T7glass alteration kinetics and their impact on long-term behavior modeling[J].J Nucl Mater,2001,298(1):27-36.

[83]VIENNA J D,RYAN J V.Current understanding and remaining challenges in modeling long-term degradation of borosilicate nuclear waste glasses[J].Int J Appl Glass Sci,2013:283-294.

[84]VERNAZ E Y,DUSSOSSOY J L.Current state of knowledge of nuclear waste glass corrosion mechanisms:The case of R7T7 glass[J].Appl Geochem,1992,7(1):13-22.

[85]GIN S,GODON N,RIBET I,et al.Long-term behavior of R7T7-type nuclear glass:Current state of knowledge and outlook[J].Mater Res Soc Symp Proc,2004,824:CC5.7.1-5.7.6.

[86]POINSSOT C,GIN S.Long-term behavior science:The cornerstone approach for reliably assessing the long-term performance of nuclear waste[J].J Nucl Mater,2012,420(1):182-192.

[87]CURTI E,CROVISIER JL,MORVAN G,et al.Long-term corrosion of two nuclear waste reference glasses (MW and SON68):A kinetic and mineral alteration study[J].Appl Geochem,2006,21(7):1152-1168.

[88]GIN S,GUITTONNEAU C,GODON N,et al.Nuclear glass durability:New insight into alteration layer properties[J].J Phys Chem C,2011,115(38):18696-18706.

[89]GIN S,ABDELOUAS A,CRISCENTI L J,et al.An international initiative on long-term behavior of high-level nuclear waste glass[J].Mater Today,2013,16(6):243-248.

[90]KIELPINSKI AL.The long-term acceleration of waste glass corrosion:A preliminary review[R].WSRC-TR-98-0306,Aiken,SC:Westinghouse Savannah River Co.,1995.

[91]BRADBURY M H,BERNER U,CURTI E,et al.The long term geochemical evolution of the nearfield of the HLW repository[R].Technical Report 12-01,NAGRA NTB 12-01,Wettingen:Nagra,2014.

[92]FREUDE E,GRAMBOW B,LUTZE W,et al.Long-term release from high level waste glass--Part IV:The effect of leaching mechanism[J].Mater Res Soc Symp Proc,1984,44:99-106.

[93]TRIVELPIECE C L,RICE J A,CLARK N L,et al.Corrosion of ISGfibers in alkaline solutions[J].J Am Ceram Soc,2017,100(10):4533-4547.

[94]STRACHAN D.Glass dissolution as a function of p H and its implications for understanding mechanisms and future experiments[J].Geochim Cosmochim Acta,2017,219:111-123.

[95]GIN S.Protective Effect of the alteration gel:A key mechanism in the long-term behavior of nuclear waste glass[J].MRS Online Proceedings Library (OPL),2011,663:207.

[96]OJOVAN M I.On alteration rate renewal stage of nuclear waste glass corrosion[J].MRS Adv,2020,5(3/4):111-120.

[97]BACON D,PIERCE E.14-Development of long-term behavior models for radioactive waste forms[C]//Ojovan M I ed.Handbook of Advanced Radioactive Waste Conditioning Technologies.Cambridge:Woodhead Publishing,2011:433-454.

[98]秦建法.蒙特卡洛法模拟玻璃固化体浸出行为的研究[D].绵阳:西南科技大学,2015.QIN Jianfa.Study on the leaching behavior og glass wasteforms by Monte Carlo simulation (in Chinese,dissertation).Mianyang:Southweste University of Science and Technology,2015.

[99]HARVEY K B.Dissolution models for glassy waste forms[R].AECL-10738,Pinawa:Whiteshell Laboratories,1995.

[100]GRAMBOW B.A general rate equation for nuclear waste glass corrosion[J].MRS Online Proceedings Library (OPL),2011,44:15.

[101]PARKHURST D,APPELO C A J.User’s guide to PHREEQC (version2)-a computer program for speciation,batch-reaction,one dimensional transport,and inverse geochemical calculations[R].Water-Resources Investigations Report 99-4259,Denver,Colorado:U.S.Department of the Interior,U.S.Geological Survey,1999.

[102]WOLERY T J.EQ3/6,A software package for geochemical modeling of aqueous systems:Package overview and installation guide (Version7.0)[R].UCRL-MA-110662 FT I,CA (United States):Lawrence Livermore National Lab.,1992:1-66.

[103]PARKHURST,DAVID L.PHREEQE-A computer program for geochemical calculations[R].Water-Resources Investigations Report80-96,United States:U.S.Geological Survey,1980.

[104]JANTZEN C M,PLODINEC M J.Thermodynamic model of natural,medieval and nuclear waste glass durability[J].J Non-Cryst Solids,1984,67(1-3):207-223.

[105]ADVOCAT T,CROVISIER J.L,FRITZ B,et al.Thermokinetic model of borosilicate glass dissolution:Contextual affinity[J].MRSOnline Proceedings Library (OPL),1989,176:241.

[106]NEDELEC J M,HENCH L L.Ab initio molecular orbital calculations on silica rings[J].J Non-Crystal Solids,1999,255(2/3):163-170.

[107]XIAO Y,LASAGA A C.Ab initio quantum mechanical studies of the kinetics and mechanisms of silicate dissolution:H+(H3O+) catalysis[J].Geochim Cosmochim Acta,1994,58(24):5379-5400.

[108]DELAYE J M,GHALEB D.Molecular dynamics simulation of Si O2-B2O3-Na2O-Zr O2 glass[J].J Non-Cryst Solids,1996,195(3):239-248.

[109]DELAYE J M,GHALEB D.Molecular dynamics analysis of volume change in a nuclear glass model subjected to a displacement cascade[J].Nucl Instrum Methods Phys Res,1999,153(1-4):157-162.

[110]冯冬青.模糊智能控制[M].北京:化学工业出版社,1998.

[111]BRAUER D S,RüSSEL C,KRAFT J.Solubility of glasses in the system P2O5-Ca O-Mg O-Na2O-Ti O2:Experimental and modeling using artificial neural networks[J].J Non-Cryst Solids,2007,353(3):263-270.

[112]AERTSENS,MARC.Testing the grambow glass dissolution model by comparing it with Monte Carlo simulation results[J].MRS Online Proceedings Library (OPL),1999,556:409.

[113]AERTSENS M,ISEGHEM P V.Modelling glass dissolution with a Monte Carlo technique[J].MRS Online Proceedings Library (OPL),1995,412:271.

[114]AERTSENS M,GHALEB D.New techniques for modelling glass dissolution[J].J Nucl Mater,2001,298(1):37-46.

[115]EWING R C.Natural glasses:Analogues for radioactive waste forms[C]//MCCARTHY G J,SCHWOEBEL R L,POTTERLL R W,et al,eds.Scientific Basis for Nuclear Waste Management.Boston,MA:Springer,1979:57-68.

[116]KAMEI G,YUSA Y,ARAI T.A natural analogue of nuclear waste glass in compacted bentonite[J].Appl Geochem,2000,15(2):141-155.

[117]VERNEY C A,GIN S,LIBOUREL G.Archaeological analogs and the future of nuclear waste glass[J].J Nucl Mater,2010,406(3):365-370.

[118]LIBOUREL F G.Long-term modeling of alteration-transport coupling:Application to a fractured Roman glass[J].Geochim Cosmochim Acta,2010,74(8):2291-2315.

[119]VERNEY C A,GIN S,LIBOUREL G.A fractured roman glass block altered for 1800 years in seawater:Analogy with nuclear waste glass in a deep geological repository[J].Geochim Cosmochim Acta,2008,72(22):5372-5385.

[120]罗上庚.地下实验室--高放废物地质处置的重要研究设施[J].辐射防护,2003,23(6):366-371.LUO Shanggeng.Radiat Protect (in Chinese),2003,23(6):366-371.

[121]CESBRON J.In situ characterization of a full scale poroelastic test section in Belgium[C]//Inter-noise&Noise-con Congress&Conference,Hamburg,Germany,2016:2082-2093.

[122]ISEGHEM P V,TIMMERMANS W,NEERDAEL B.In-situ testing of nuclear waste glasses in a clay laboratory-Results after two years corrosion[J].MRS Online Proceedings Library (OPL),1989,176:283-289.

[123]GARAVITO A M,CANNIèRE P D,KOOI H.In situ chemical osmosis experiment in the Boom Clay at the Mol underground research laboratory[J].Phys Chem Earth,2007,32:421-433.

[124]ISEGHEM P V,VALCKE E,LODDING A.In situ testing of the chemical durability of vitrified high-level waste in a Boom Clay formation in Belgium:Discussion of recent data and concept of a new test[J].J Nucl Mater,2001,298(1):86-94.

[125]CHO W J,KWON S,PARK J H.KURT,A small-scale underground research laboratory for the research on a high-level waste disposal[J].Ann Nucl Energy,2008,35(1):132-140.

[126]MCELROY J,BJORKLUND W,BONNER W.Waste vitrification:Ahistorical perspective[R].Richland,Washington:Pacific Northwest Lab,1982.

[127]BONNIAUD R,SOMBRET C,BARBE A.French industrial plant AVM for continuous vitrification of high level radioactive wastes[R].CEA-CONF-3559,France:CEA,1975:1-19.

[128]李恒腾.卡尔斯鲁厄研究所高放废液的玻璃固化试验装置投入运行[J].国外核新闻,1980(17):23.LI Hengteng.Foreign Nuclear News (in Chinese),1980(17):23.

[129]SASAKI N,KARINO M,KASHIHARA H,et al.Solidification of the high-level liquid waste from the Tokai reprocessing plant[C]//Fuel reprocessing and waste management.Volume 1,United States,1984.

[130]BORISCH RR,LEAP DR:The design and construction of the West Valley demonstration project vitrification facility[C]//Waste processing,transportation,storage and disposal,technical programs and public education,United States,1989.

[131]HARRISON M T.Vitrification of high level waste in the UK[J].Procedia Mater Sci,2014,7:10-15.

[132]MENDEL J E,ROSS W A,ROBERTS F P,et al.Annual report on the characteristics of high-level waste glasses[R].BNWL-2252,Richland,WA:Battelle Pacific Northwest Labs,1977.

[133]GOLDMAN M,SERVIZI J,DANIELS R,et al.Retention of fission products in ceramic glaze-type fusions[R].Cambridge:Massachusetts Institute of Technology,1958.

[134]ELIASSEN R,GOLDMAN M I.Disposal of high-level wastes by fixation in fused ceramics[C]//DOAN R L ed.Hearings on Industrial Radioactive Waste Disposal,3rd ed.Washington:US Government Printing Office,1959:1966-1979.

[135]VIENNA J,KIM D,HRMA P.Database and Interim glass property models for Hanford HLW and LAW glasses[R].PNNL-14060,Richland,Washington:Pacific Northwest National Laboratory,2002.

[136]HRMA P,PIEPEL G F,VIENNA J D,COOLEY S K,KIM D S.Database and interim glass property models for Hanford HLWglasses[R].PNNL-13573,Richland,Washington:Pacific Northwest National Laboratory,2001.

[137]VIENNA J D,FLUEGEL A,KIM D S,HRMA P.Glass property data and models for estimating high-level waste glass volume[R].PNNL-18501,Richland,Washington:Pacific Northwest National Laboratory,2009.

[138]VIENNA J D,SKORSKI D C,KIM D S,MATYAS J.Glass property models and constraints for estimating the glass to be produced at Hanford by implementing current advanced glass formulation efforts[R].PNNL-22631,Richland,Washington:Pacific Northwest National Laboratory,2013.

[139]DESCAMP V A,MCMAHON C L.Vitrification facility at the West Valley demonstration project[R].DOE/NE/44139-77,United States:Waste Valley Nuclear Services Co.,Inc.,1996.

[140]RAY JW,CULBERTSON BH,MARRA SL,et al.DWPF glass product control program[R].WSRC-IM-91-116-6,Aiken,SC:Savannah River National Laboratory,2004.

[141]BRICKER J M,FELLINGER T L,STAUB A V.Progress of the high level waste program at the defense waste processing facility[C]//WM2013 Conference,Phoenix,AZ,2013:13178.

[142]PEREZ J M,BARNES S M,KELLY S,et al.Vitrification testing and demonstration for the hanford waste treatment and immobilization plant[C]//VIENNA J,HERMAN C,MARRA S ed.Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries X,United States:The American Ceramic Society,2012:3-20.

[143]HEIMERL W.Techniques for High level waste solidification in Europe[C]//MCCARTHY G J,SCHWOEBEL R L,POTTERLL R W,et al,eds.Scientific Basis for Nuclear Waste Management,Boston,MA:Springer,1979:21-29.

[144]MASSON H,DESVAUX J,PLUCHE E,et al.The R7/T7 vitrification at La Hague:10 years of operation[R].IAEA-SM-357/33,France,2001.

[145]BRUEZIERE J,CHAUVIN E,PIROUX J.World first in high level waste vitrification--A review of French vitrification industrial achievements[C]//Proceedings of GLOBAL 2013:International Nuclear Fuel Cycle Conference-Nuclear Energy at a Crossroads,United States,2013.

[146]BRADSHAW K,GRIBBLE N,HUGHES D,et al.UK Full-scale non-active vitrification development and implementation of research findings onto the waste vitrification plant[C]//Proceedings of Waste Management 2007 Conference,Tucson AZ,2007.

[147]GEIPEL H.German Nuclear high-level waste program-Key research areas[J].MRS Online Proceedings Library (OPL),1985,50:45-48.

[148]FLEISCH J,GRUENEWALD W,PFEIFER W,et al.Radioactive start-up of the German VEK vitrification plant[C]//WM2010Conference,Phoenix,AZ,2010:10089.

[149]FLEISCH J,SCHWAAB E,WEISHAUPT M,et al.Cold test operation of the German VEK vitrification plant[C]//WM2008Conference,Phoenix,AZ,2008:8326.

[150]李玉松,张生栋,鲜亮,等.CIAE高放废液固化技术研发进展[J].原子能科学技术,2020,54:126-136.LI Yusong,ZHANG Shengdong,XIAN Liang,et al.Atom Energy Sci Technol (in Chinese),2020,54:126-136.

[151]姜耀中,汤宝龙,张宝善,等.821厂高放废液固化用基础玻璃配方的研制[J].原子能科学技术,1995,29(3):253-261.JIANG Yaozhong,TANG Baolong,ZHANG Baoshan,et al.Atom Energy Sci Technol (in Chinese),1995,29(3):253-261.

[152]刘丽君,郄东生,李扬,等.冷坩埚玻璃固化模拟高放废液的24 h连续运行实验研究[J].原子能科学技术,2018,52(12):108-115.LIU Lijun,QIE Dongsheng,LI Yang,et al.Atom Energy Sci Technol(in Chinese),2018,52(12):108-115.

[153]SOBOLEV I A,DMITRIEV S,LIFANOV F A,et al.Vitrification processes for low,intermediate radioactive and mixed wastes[J].Glass Technol-Eur J Glass Sci Technol Part A,2005,46:28-35.

[154]OH C H.Hazardous and Radioactive Waste Treatment Technologies Handbook[M].United States:CRC Press,2001.

[155]卢嘉炜,郭子方,吴志豪,等.日本高放废液玻璃固化技术[J].辐射防护,2020(1):67-77.LU Jiawei,GUO Zifang,WU Zhihao,et al.Radiatn Protect (in Chinese),2020(1):67-77.

[156]廖其龙,蔺海艳,王辅,等.Na2O/Al2O3摩尔比对模拟高放废液硼硅酸盐玻璃固化体结构和性能的影响[J].核化学与放射化学,2014,36(4):235-240.LIAO Qilong,LIN Haiyan,WANG Fu,et al.J Nucl Radiochem (in Chinese),2014,36(4):235-240.

[157]张华,李扬,李宝军,等.动力堆高放废物对硼硅酸盐玻璃体结构影响研究[C]//废物地下处置学术研讨会,2016.

[158]李江波,李扬,李宝军,等.掺加铬对硼硅酸盐玻璃固化体结构影响[J].功能材料,2017,48(7):07209-07214.LI Jiangbo,LI Yang,LI Baojun,et al.J Funct Mater (in Chinese),2017,48(7):07209-07214.

[159]刘丽君.我国高放废液玻璃固化技术四十年的发展[C]//中国核学会2015年学术年会,2015:389-393.

[160]ROBERT S,GUILBERT F G,CARPENTIER B,et al.A milestone in vitrification:The replacement of a“hot metallic crucible”With a“cold crucible melter”in a hot cell at the La Hague plant,France[C]//ASME2010 International Conference on Environmental Remediation and Radioactive Waste Management,2010.

[161]张华,罗上庚,姜耀中,等.低氧条件下浸出剂和温度对固化体浸出行为的影响[J].核化学与放射化学,2005,27(3):144-151.ZHANG Hua,LUO Shanggeng,JIANG Yaozhong,et al.J Nucl Radiochem (in Chinese),2005,27(3):144-151.

[162]吴兆广.GC-12/9B硼硅酸盐模拟高放废物玻璃固化体在模拟处置条件下的浸出行为研究[D].北京:中国原子能科学研究院,1990.WU Zhaoguang.Study on leaching behavior of GC-12/9B borosilicate simulated high-level radioactive waste glass solidified body under simulated disposal conditions (in Chinese,dissertation).Beijing:China Institute of Atomic Energy,1990.

[163]吴兆广,罗上庚,于承泽,等.模拟高放废物玻璃固化体在处置条件下的浸出行为研究(Ⅰ)[J].核科学与工程,1994,14(4):340-349.WU Zhaoguang,LUO Shanggeng,YU Chengze,et al.Chin J Nucl Sci Eng (in Chinese),1994,14(4):340-349.

[164]吴兆广,罗上庚,于承泽,等.模拟高放废物玻璃固化体在处置条件下的浸出行为研究(Ⅱ)[J].核科学与工程,1996,16(1):87-93.WU Zhaoguang,LUO Shanggeng,YU Chengze,et al.Chin J Nucl Sci Eng (in Chinese),1996,16(1):87-93.