Neutronic analysis of ITER radial x-ray camera
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摘要
The radial x-ray camera(RXC) is designed to measure the poloidal profile of plasma x-ray emission with high spatial and temporal resolution. The RXC diagnostic system consists of internal camera module and external camera module that view the core region and outer region through the vertical slots of the diagnostic first wall and diagnostics shield module of the equatorial port plug. To ensure the normal performance of the silicon photodiode array detectors of the cameras in the hard neutron irradiation environment in ITER tokamak, it is necessary to calculate neutron flux, radiation damage and the nuclear heating of the silicon photodiode array detectors and simulate the radiation maps of the range of RXC. This work estimated the nuclear environment of RXC based on Monte Carlo N-particle transport code, plasma scenarios of ITER tokamak and the RXC-integrated ITER CLITE model. The neutron flux of silicon photodiode array detectors and the lifetime of the silicon photodiode detector in the camera were calculated. The neutronic analysis results show that the shielding design has achieved the effect as expected and is able to guarantee the normal work of the detector during the ITER deuterium–deuterium phase without replacement, three detectors of the external camera can be operated during the whole deuterium–tritium phase without replacement.
The radial x-ray camera(RXC) is designed to measure the poloidal profile of plasma x-ray emission with high spatial and temporal resolution. The RXC diagnostic system consists of internal camera module and external camera module that view the core region and outer region through the vertical slots of the diagnostic first wall and diagnostics shield module of the equatorial port plug. To ensure the normal performance of the silicon photodiode array detectors of the cameras in the hard neutron irradiation environment in ITER tokamak, it is necessary to calculate neutron flux, radiation damage and the nuclear heating of the silicon photodiode array detectors and simulate the radiation maps of the range of RXC. This work estimated the nuclear environment of RXC based on Monte Carlo N-particle transport code, plasma scenarios of ITER tokamak and the RXC-integrated ITER CLITE model. The neutron flux of silicon photodiode array detectors and the lifetime of the silicon photodiode detector in the camera were calculated. The neutronic analysis results show that the shielding design has achieved the effect as expected and is able to guarantee the normal work of the detector during the ITER deuterium–deuterium phase without replacement, three detectors of the external camera can be operated during the whole deuterium–tritium phase without replacement.
The radial x-ray camera(RXC) is designed to measure the poloidal profile of plasma x-ray emission with high spatial and temporal resolution. The RXC diagnostic system consists of internal camera module and external camera module that view the core region and outer region through the vertical slots of the diagnostic first wall and diagnostics shield module of the equatorial port plug. To ensure the normal performance of the silicon photodiode array detectors of the cameras in the hard neutron irradiation environment in ITER tokamak, it is necessary to calculate neutron flux, radiation damage and the nuclear heating of the silicon photodiode array detectors and simulate the radiation maps of the range of RXC. This work estimated the nuclear environment of RXC based on Monte Carlo N-particle transport code, plasma scenarios of ITER tokamak and the RXC-integrated ITER CLITE model. The neutron flux of silicon photodiode array detectors and the lifetime of the silicon photodiode detector in the camera were calculated. The neutronic analysis results show that the shielding design has achieved the effect as expected and is able to guarantee the normal work of the detector during the ITER deuterium–deuterium phase without replacement, three detectors of the external camera can be operated during the whole deuterium–tritium phase without replacement.
引文
[1]Suarez A et al 2015 Fusion Eng.Des.98-99 1427
[2]Colling B et al 2016 Fusion Eng.Des.109-111 1109
[3]Costley A E et al 2008 Measurement requirements and the diagnostic system on ITER:modifications following the design review Proc.22nd IAEA Fusion Energy Conf.(Geneva,Switzerland)(International Atomic Energy Agency)
[4]Wang S K et al 2013 Electromagnetic behavior on ITER radial soft x-ray camera Proc.25th Symp.on Fusion Engineering(San Francisco,CA)(IEEE)2013
[5]Hu L et al 2016 Fusion Sci.Technol.70 112
[6]Vayakis G 2014 Current status of ITER diagnostics development Proc.26th ITPA Topical Group Spring Mtg(Pohang,South Korea)(https://portal.iter.org/departments/POP/ITPA/Diag/DIAG)
[7]Hu L et al 2017 Nucl.Instrum.Methods Phys.Res.A 870 50
[8]Hu L et al 2014 Progress on the ITER diagnostic-radial x-ray camera Proc.25th IAEA Fusion Energy Conf.(Saint Petersburg,Russian Federation)(International Atomic Energy Agency)
[9]X-5 Monte Carlo Team 2003 MCNP-A general Monte Carlo N-particle Transport Code Version 5 LA-UR-03-1987 Los Alamos National Laboratory
[10]Polunovskiy E 2013 ITER_D_JLDCY7,Status of C-Lite:https://user.iter.org/default.aspx?uid=JLDCY7
[11]Kim J W et al 2015 Fusion Sci.Technol.68 652
[12]Wu Y and Team F D S 2009 Fusion Eng.Des.84 1987
[13]Davis A and Turner A 2011 Fusion Eng.Des.86 2698
[14]Aldama D L and Trkov A 2004 FENDL-2.1:Evaluated Nuclear Data Library for Fusion Applications IAEA Report INDC(NDS)-467,FENDL-2.1 Library Home:http://nds.iaea.org/fendl21/
[15]Zhu Q J,Li J and Liu S L 2016 Plasma Sci.Technol.18 775
[16]Alper B et al 1997 Rev.Sci.Instrum.68 778
[17]Kohagura J et al 2003 Nucl.Instrum.Methods Phys.Res.A513 300
[18]Campbell D 2009 ITER_D_2FB8AC,ITER Research Plan:https://user.iter.org/default.aspx?uid=2FB8AC
[19]Dentan M 2013 ITER_D_KR6349,Outcome of RHA-CM-003 side meeting on simplified radiation maps:https://user.iter.org/default.aspx?uid=KR6349
[2]Colling B et al 2016 Fusion Eng.Des.109-111 1109
[3]Costley A E et al 2008 Measurement requirements and the diagnostic system on ITER:modifications following the design review Proc.22nd IAEA Fusion Energy Conf.(Geneva,Switzerland)(International Atomic Energy Agency)
[4]Wang S K et al 2013 Electromagnetic behavior on ITER radial soft x-ray camera Proc.25th Symp.on Fusion Engineering(San Francisco,CA)(IEEE)2013
[5]Hu L et al 2016 Fusion Sci.Technol.70 112
[6]Vayakis G 2014 Current status of ITER diagnostics development Proc.26th ITPA Topical Group Spring Mtg(Pohang,South Korea)(https://portal.iter.org/departments/POP/ITPA/Diag/DIAG)
[7]Hu L et al 2017 Nucl.Instrum.Methods Phys.Res.A 870 50
[8]Hu L et al 2014 Progress on the ITER diagnostic-radial x-ray camera Proc.25th IAEA Fusion Energy Conf.(Saint Petersburg,Russian Federation)(International Atomic Energy Agency)
[9]X-5 Monte Carlo Team 2003 MCNP-A general Monte Carlo N-particle Transport Code Version 5 LA-UR-03-1987 Los Alamos National Laboratory
[10]Polunovskiy E 2013 ITER_D_JLDCY7,Status of C-Lite:https://user.iter.org/default.aspx?uid=JLDCY7
[11]Kim J W et al 2015 Fusion Sci.Technol.68 652
[12]Wu Y and Team F D S 2009 Fusion Eng.Des.84 1987
[13]Davis A and Turner A 2011 Fusion Eng.Des.86 2698
[14]Aldama D L and Trkov A 2004 FENDL-2.1:Evaluated Nuclear Data Library for Fusion Applications IAEA Report INDC(NDS)-467,FENDL-2.1 Library Home:http://nds.iaea.org/fendl21/
[15]Zhu Q J,Li J and Liu S L 2016 Plasma Sci.Technol.18 775
[16]Alper B et al 1997 Rev.Sci.Instrum.68 778
[17]Kohagura J et al 2003 Nucl.Instrum.Methods Phys.Res.A513 300
[18]Campbell D 2009 ITER_D_2FB8AC,ITER Research Plan:https://user.iter.org/default.aspx?uid=2FB8AC
[19]Dentan M 2013 ITER_D_KR6349,Outcome of RHA-CM-003 side meeting on simplified radiation maps:https://user.iter.org/default.aspx?uid=KR6349