Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR
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摘要
The water-cooled ceramic breeder(WCCB)blanket is one of the blanket candidates for Chinese fusion engineering testing reactor(CFETR)and is being developed at the Institute of Plasma Physics,Chinese Academy of Sciences(ASIPP).This paper reviews design and evolution of the WCCB blanket for CFETR,and presents a new WCCB blanket design according to the latest CFETR core parameters(major and minor radii are R=7.2 m and a=2.2 m,respectively)and missions.This new design is expected to satisfy multiple CFETR operation modes of 0.2,0.5,1.0,and 1.5 GW fusion power and achieve tritium self-sufficiency.The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics.Furthermore,the research and development(R&D)activities supporting to the WCCB blanket for CFETR are reported,including the design code,the water loop experiments,the pebble bed modeling and experiments,and the components fabrication technology.
The water-cooled ceramic breeder(WCCB)blanket is one of the blanket candidates for Chinese fusion engineering testing reactor(CFETR)and is being developed at the Institute of Plasma Physics,Chinese Academy of Sciences(ASIPP).This paper reviews design and evolution of the WCCB blanket for CFETR,and presents a new WCCB blanket design according to the latest CFETR core parameters(major and minor radii are R=7.2 m and a=2.2 m,respectively)and missions.This new design is expected to satisfy multiple CFETR operation modes of 0.2,0.5,1.0,and 1.5 GW fusion power and achieve tritium self-sufficiency.The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics.Furthermore,the research and development(R&D)activities supporting to the WCCB blanket for CFETR are reported,including the design code,the water loop experiments,the pebble bed modeling and experiments,and the components fabrication technology.
The water-cooled ceramic breeder(WCCB)blanket is one of the blanket candidates for Chinese fusion engineering testing reactor(CFETR)and is being developed at the Institute of Plasma Physics,Chinese Academy of Sciences(ASIPP).This paper reviews design and evolution of the WCCB blanket for CFETR,and presents a new WCCB blanket design according to the latest CFETR core parameters(major and minor radii are R=7.2 m and a=2.2 m,respectively)and missions.This new design is expected to satisfy multiple CFETR operation modes of 0.2,0.5,1.0,and 1.5 GW fusion power and achieve tritium self-sufficiency.The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics.Furthermore,the research and development(R&D)activities supporting to the WCCB blanket for CFETR are reported,including the design code,the water loop experiments,the pebble bed modeling and experiments,and the components fabrication technology.
引文
[1]Y.X.Wan,J.G.Li,Present progresses and activities on the Chinese Fusion Engineering Test Reactor.in:SOFT 2018 Conference.
[2]S.L.Liu,X.B.Ma,X.M.Cheng,et al.,Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology,Fusion Eng.Des.124(2017)865-870.
[3]S.L.Liu,Y.Pu,X.M.Cheng,et al.,Conceptual design of a water cooled breeder blanket for CFETR,Fusion Eng.Des.89(2014)1380-1385.
[4]A.Del Nevo,E.Martelli,P.Agostini,et al.,WCLL breeding blanket design and integration for DEMO 2015:status and perspectives,Fusion Eng.Des.124(2017)682-686.
[5]S.L.Liu,X.Li,X.B.Ma,et al.,Updated design of water-cooled breeder blanket for CFETR.Fusion Eng.Des.(2019)in press.doi:10.1016/j.fusengdes.2019.03.023
[6]K.C.Jiang,X.B.Ma,X.M.Cheng,et al.,Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR,Fusion Eng.Des.112(2016)81-88.
[7]K.C.Jiang,J.Li,X.K.Zhang,et al,The development and application of one thermal-hydraulic program based on ANSYS for design of ceramic breeder blanket of CFETR0,Fusion Eng.Des.34(2015)1088-1093.
[8]J.Li,K.C.Jiang,X.K.Zhang,et al.,Nuclear-thermal-coupled optimization code for the fusion breeding blanket conceptual design,Fusion Eng.Des.113(2016)37-42.
[9]K.C.Jiang,W.Q.Ding,X.K.Zhang,et al.,Development of neutronic-thermal hydraulic-mechanic-coupled platform for WC-CB blanket design for CFETR,Fusion Eng.Des.137(2018)312-324.
[10]K.C.Jiang,X.K.Zhang,J.Li,et al.,Using one hybrid 3D-1D-3Dapproach for the conceptual design of WCCB blanket for CFETR,Fusion Eng.Des.114(2017)57-71.
[11]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on natural circulation heat transfer of square channel in water cooled blanket,IEEE Trans.Plasma.Sci.46(2018)2291-2300.
[12]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on the natural circulation subcooled boiling of square channel in fusion reactor blanket,Energy Procedia.144(2018)186-194.
[13]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on the dryout point and post-dryout heat transfer in square channel.,Fusion Eng.Des.136(2018)1012-1018.
[14]S.L.Liu,K.Huang,Y.H.Chen,et al.,Numerical and experimental study on pebble bed flow characterics for water cooled ceramic breeder blanket of CFETR,in:International Workshop on Mechanics of Energy Materials,Suzhou,China,2017.
[15]C.Wang,L.Chen,S.L.Liu,Effective thermal conductivity of unitary and binary pebble beds:numerical prediction and experimental measurement,in:International Workshop on Mechanics of Energy Materials,Chennai,India,2018.
[16]L.Chen,Y.H.Chen,K.Huang,et al.,Investigation of the packing structure of pebble beds by DEM for CFETR WCCB,J.Nucl.Sci.Technol.53(2016)803-808.
[17]Y.H.Chen,L.Chen,S.L.Liu,et al.,Flow characteristics analysis of purge gas in unitary pebble beds by CFD simulation coupled with DEM geometry model for fusion blanket,Fusion Eng.Des.114(2017)84-90.
[18]L.Chen,Y.H.Chen,K.Huang,et al.,Investigation of effectivethermal conductivity for pebble beds by one-way coupled CFD-DEM method for CFETR WCC,Fusion Eng.Des.106(2016)1-8.
[19]L.Chen,C.Wang,M.Moscardini,et al.,A DEM-based heat transfer model for the evaluation of effective thermal conductivity of packed beds filled with stagnant fluid:Thermal contact theory and numerical simulation,Int.J.Heat Mass Trans.132(2019)331-346.
[20]J.C.Wang,W.J.Wang,Z.X.Sun,et al.,Microstructure and mechanical analysis of W/P91 steel HIP-joint with Ti interlayer,Fusion Eng.Des.112(2016)67-73.
[21]J.C.Wang,W.J.Wang,R.Wei,et al.,Effect of Ti interlayer on the bonding quality of W and steel HIP joint,J.Nucl.Mat.485(2017)8-14.
[22]J.C.Wang,J.J.Huang,H.B.Sun,et al.,Effect of deuterium on bonding quality of W/Ti/Steel HIP joints in first wall application,Fusion Eng.Des.138(2019)313-320.
[2]S.L.Liu,X.B.Ma,X.M.Cheng,et al.,Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology,Fusion Eng.Des.124(2017)865-870.
[3]S.L.Liu,Y.Pu,X.M.Cheng,et al.,Conceptual design of a water cooled breeder blanket for CFETR,Fusion Eng.Des.89(2014)1380-1385.
[4]A.Del Nevo,E.Martelli,P.Agostini,et al.,WCLL breeding blanket design and integration for DEMO 2015:status and perspectives,Fusion Eng.Des.124(2017)682-686.
[5]S.L.Liu,X.Li,X.B.Ma,et al.,Updated design of water-cooled breeder blanket for CFETR.Fusion Eng.Des.(2019)in press.doi:10.1016/j.fusengdes.2019.03.023
[6]K.C.Jiang,X.B.Ma,X.M.Cheng,et al.,Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR,Fusion Eng.Des.112(2016)81-88.
[7]K.C.Jiang,J.Li,X.K.Zhang,et al,The development and application of one thermal-hydraulic program based on ANSYS for design of ceramic breeder blanket of CFETR0,Fusion Eng.Des.34(2015)1088-1093.
[8]J.Li,K.C.Jiang,X.K.Zhang,et al.,Nuclear-thermal-coupled optimization code for the fusion breeding blanket conceptual design,Fusion Eng.Des.113(2016)37-42.
[9]K.C.Jiang,W.Q.Ding,X.K.Zhang,et al.,Development of neutronic-thermal hydraulic-mechanic-coupled platform for WC-CB blanket design for CFETR,Fusion Eng.Des.137(2018)312-324.
[10]K.C.Jiang,X.K.Zhang,J.Li,et al.,Using one hybrid 3D-1D-3Dapproach for the conceptual design of WCCB blanket for CFETR,Fusion Eng.Des.114(2017)57-71.
[11]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on natural circulation heat transfer of square channel in water cooled blanket,IEEE Trans.Plasma.Sci.46(2018)2291-2300.
[12]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on the natural circulation subcooled boiling of square channel in fusion reactor blanket,Energy Procedia.144(2018)186-194.
[13]H.Bao,Y.Guo,S.L.Liu,et al.,Experimental study on the dryout point and post-dryout heat transfer in square channel.,Fusion Eng.Des.136(2018)1012-1018.
[14]S.L.Liu,K.Huang,Y.H.Chen,et al.,Numerical and experimental study on pebble bed flow characterics for water cooled ceramic breeder blanket of CFETR,in:International Workshop on Mechanics of Energy Materials,Suzhou,China,2017.
[15]C.Wang,L.Chen,S.L.Liu,Effective thermal conductivity of unitary and binary pebble beds:numerical prediction and experimental measurement,in:International Workshop on Mechanics of Energy Materials,Chennai,India,2018.
[16]L.Chen,Y.H.Chen,K.Huang,et al.,Investigation of the packing structure of pebble beds by DEM for CFETR WCCB,J.Nucl.Sci.Technol.53(2016)803-808.
[17]Y.H.Chen,L.Chen,S.L.Liu,et al.,Flow characteristics analysis of purge gas in unitary pebble beds by CFD simulation coupled with DEM geometry model for fusion blanket,Fusion Eng.Des.114(2017)84-90.
[18]L.Chen,Y.H.Chen,K.Huang,et al.,Investigation of effectivethermal conductivity for pebble beds by one-way coupled CFD-DEM method for CFETR WCC,Fusion Eng.Des.106(2016)1-8.
[19]L.Chen,C.Wang,M.Moscardini,et al.,A DEM-based heat transfer model for the evaluation of effective thermal conductivity of packed beds filled with stagnant fluid:Thermal contact theory and numerical simulation,Int.J.Heat Mass Trans.132(2019)331-346.
[20]J.C.Wang,W.J.Wang,Z.X.Sun,et al.,Microstructure and mechanical analysis of W/P91 steel HIP-joint with Ti interlayer,Fusion Eng.Des.112(2016)67-73.
[21]J.C.Wang,W.J.Wang,R.Wei,et al.,Effect of Ti interlayer on the bonding quality of W and steel HIP joint,J.Nucl.Mat.485(2017)8-14.
[22]J.C.Wang,J.J.Huang,H.B.Sun,et al.,Effect of deuterium on bonding quality of W/Ti/Steel HIP joints in first wall application,Fusion Eng.Des.138(2019)313-320.