Considering for the blanket structure scheme of HCCB DEMO
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摘要
For the solid blanket concept of helium cooled ceramic breeder(HCCB)demonstration fusion power plant(DEMO),a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier beryllium pebbles.Based on that,preliminary design for the typical blanket module of HCCB DEMO has been carried out and verified by thermal-hydraulic analysis and structural analysis.Furthermore,the specific relationship of maximum temperature depended on the surface heating of blanket key part first wall(FW)is also analyzed.
For the solid blanket concept of helium cooled ceramic breeder(HCCB)demonstration fusion power plant(DEMO),a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier beryllium pebbles.Based on that,preliminary design for the typical blanket module of HCCB DEMO has been carried out and verified by thermal-hydraulic analysis and structural analysis.Furthermore,the specific relationship of maximum temperature depended on the surface heating of blanket key part first wall(FW)is also analyzed.
For the solid blanket concept of helium cooled ceramic breeder(HCCB)demonstration fusion power plant(DEMO),a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier beryllium pebbles.Based on that,preliminary design for the typical blanket module of HCCB DEMO has been carried out and verified by thermal-hydraulic analysis and structural analysis.Furthermore,the specific relationship of maximum temperature depended on the surface heating of blanket key part first wall(FW)is also analyzed.
引文
[1]C.H.Pan,Y.C.Wu,K.M.Feng,et al.,DEMO development strategy based on China FPP program,Fusion Engineering and Design 83(2008)877-882.
[2]K.M.Feng,G.S.Zhang,G.Y.Zheng,et al.,Conceptual design study of fusion DEMO plant at SWIP,Fusion Engineering and Design 84(2009)2109-2113.
[3]N.Bekris,L.V.Boccaccini,S.Dolenski,et al.,Design Description Document for the European Helium Cooled Pebble Bed(HCPB)Test Blanket Modules,Forschungszentrum Karlsruhe,2005.
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[5]Y.X.Wan,J.G.Li,Y.Liu,et al.,Overview of the present progress and activities on the CFETR,Nuclear Fusion 57(2017)102009.
[6]L.M.Giancarli,M.Abdou,D.J.Campbell,et al.,Overview of the ITER TBM Program,Fusion Engineering and Design 87(2012)395-402.
[7]M.Abdou,N.B.Morley,S.Smolentsev,et al.,Blanket/first wall challenges and required R&D on the pathway to DEMO,Fusion Engineering and Design 100(2015)2-43.
[8]Z.Zhao,G.Hu,Q.-J.Wang,et al.,Structural design for the back plate of submodule of CH HCCB TBM with 1×4 configuration,Nuclear Fusion and Plasma Physics 34(2014)224-229.
[9]K.M.Feng,X.Y.Wang,Y.J.Feng,et al.,Current progress of Chinese HCCB TBM program,Fusion Engineering and Design109-111(2016)729-735.
[10]F.Cismondi,S.Kecskés,M.Ilic,et al.,Design update,thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement,Fusion Engineering and Design 84(2009)607-612.
[11]M.Zmitko,N.Thomas,A.Lipuma,et al.,The European ITERtest blanket modules:Progress in development of fabrication technologies towards standardization,Fusion Engineering and Design 109-111(2016)1687-1691.
[12]D.Aquaro,N.Cerullo,I.Ciucci,et al.,Adaptation of the HCPBDEMO TBM as breeding blanket for ITER:Neutronic and thermal analyses,Fusion Engineering and Design 82(2007)2226.
[13]A.Abou-Sena,H.Neuberger,T.Ihli,Experimental investigation on the possible techniques of pebbles packing for the HCPB Test Blanket Module,Fusion Engineering and Design 84(2009)355-358.
[14]S.H Wang,Q.X.Cao,X.H.Wu,et al.,Updated conceptual design of helium cooling ceramic blanke for HCCB-DEMO,Fusion Engineering and Design 112(2016)148-155.
[15]P.Norajitra,Thermo-hydraulics Design and Thermo-mechanics Analysis of Two European Breeder Blanket Concepts for DEMO,Forschungszentrum Karlsruhe,1995.
[16]S.H.Wang,Helium Cooling Ceramic Breeder Blanket Design for fusion DEMO(HCCB DEMO),University of Science and Technology of China,2016.
[17]AFCEN,Design and Construction for Mechanical Components of FBR nuclear islands(RCC-MR),AFCEN,2007.
[18]Y.J.Feng,P.H.Wang,HCCB-TBS Material Summary for EM/Thermal/Structural Analysis,ITER Orgnization,2014.
[19]M.Zmitko,Y.Poitevin,I.Ricapito,et al.,Proposal for the EUHCLL and HCPB TBMs ESP/ESPN classification,ITER Orgnization,2012.
[20]D.Carloni,L.V.Boccaccini,F.Franza,et al.,Requirements for helium cooled pebble bed blanket and R&D activities,Fusion Engineering and Design 89(2014)1341-1345.
[2]K.M.Feng,G.S.Zhang,G.Y.Zheng,et al.,Conceptual design study of fusion DEMO plant at SWIP,Fusion Engineering and Design 84(2009)2109-2113.
[3]N.Bekris,L.V.Boccaccini,S.Dolenski,et al.,Design Description Document for the European Helium Cooled Pebble Bed(HCPB)Test Blanket Modules,Forschungszentrum Karlsruhe,2005.
[4]O.Motojima,The ITER project construction status,Nuclear Fusion 55(2015)104023.
[5]Y.X.Wan,J.G.Li,Y.Liu,et al.,Overview of the present progress and activities on the CFETR,Nuclear Fusion 57(2017)102009.
[6]L.M.Giancarli,M.Abdou,D.J.Campbell,et al.,Overview of the ITER TBM Program,Fusion Engineering and Design 87(2012)395-402.
[7]M.Abdou,N.B.Morley,S.Smolentsev,et al.,Blanket/first wall challenges and required R&D on the pathway to DEMO,Fusion Engineering and Design 100(2015)2-43.
[8]Z.Zhao,G.Hu,Q.-J.Wang,et al.,Structural design for the back plate of submodule of CH HCCB TBM with 1×4 configuration,Nuclear Fusion and Plasma Physics 34(2014)224-229.
[9]K.M.Feng,X.Y.Wang,Y.J.Feng,et al.,Current progress of Chinese HCCB TBM program,Fusion Engineering and Design109-111(2016)729-735.
[10]F.Cismondi,S.Kecskés,M.Ilic,et al.,Design update,thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement,Fusion Engineering and Design 84(2009)607-612.
[11]M.Zmitko,N.Thomas,A.Lipuma,et al.,The European ITERtest blanket modules:Progress in development of fabrication technologies towards standardization,Fusion Engineering and Design 109-111(2016)1687-1691.
[12]D.Aquaro,N.Cerullo,I.Ciucci,et al.,Adaptation of the HCPBDEMO TBM as breeding blanket for ITER:Neutronic and thermal analyses,Fusion Engineering and Design 82(2007)2226.
[13]A.Abou-Sena,H.Neuberger,T.Ihli,Experimental investigation on the possible techniques of pebbles packing for the HCPB Test Blanket Module,Fusion Engineering and Design 84(2009)355-358.
[14]S.H Wang,Q.X.Cao,X.H.Wu,et al.,Updated conceptual design of helium cooling ceramic blanke for HCCB-DEMO,Fusion Engineering and Design 112(2016)148-155.
[15]P.Norajitra,Thermo-hydraulics Design and Thermo-mechanics Analysis of Two European Breeder Blanket Concepts for DEMO,Forschungszentrum Karlsruhe,1995.
[16]S.H.Wang,Helium Cooling Ceramic Breeder Blanket Design for fusion DEMO(HCCB DEMO),University of Science and Technology of China,2016.
[17]AFCEN,Design and Construction for Mechanical Components of FBR nuclear islands(RCC-MR),AFCEN,2007.
[18]Y.J.Feng,P.H.Wang,HCCB-TBS Material Summary for EM/Thermal/Structural Analysis,ITER Orgnization,2014.
[19]M.Zmitko,Y.Poitevin,I.Ricapito,et al.,Proposal for the EUHCLL and HCPB TBMs ESP/ESPN classification,ITER Orgnization,2012.
[20]D.Carloni,L.V.Boccaccini,F.Franza,et al.,Requirements for helium cooled pebble bed blanket and R&D activities,Fusion Engineering and Design 89(2014)1341-1345.