ITER极向场线圈维修过程及照射剂量虚拟仿真
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- 英文论文题名：Virtual reality-based Simulation for Occupational Radiation Exposure Assessment during ITER PF4 Maintenance
- 论文作者：何桃 ; 赵锦波 ; 张澍 ; 杨子辉 ; 胡丽琴 ; FDS团队
- 英文论文作者：Tao HE ; Jinbo ZHAO ; Shu ZHANG ; Zihui YANG ; Liqin HU ; FDS Team ; Institute of Nuclear Energy Safety Technology ; Chinese Academy of Sciences ; Hefei of Anhui Prov. ; University of Science and Technology of China ; Hefei of Anhui Prov.
- 年：2014
- 作者机构：中国科学院核能安全技术研究所;中国科学技术大学;
- 论文关键词：ITER ; 职业照射剂量 ; 虚拟仿真 ; 极向场线圈 ; RVIS
- 英文论文关键词：ITER ; Occupational Radiation Exposure ; Virtual reality Simulation ; PF4 ; RVIS
- 会议召开时间：2014-08-13
- 会议录名称：第十七届全国核电子学与核探测技术学术年会论文集
- 语种：中文
- 分类号：TL622
- 学会代码：HDZX
- 会议名称：第十七届全国核电子学与核探测技术学术年会
- 会议地点：中国甘肃兰州
- 主办单位：中国电子学会、中国核学会核电子学与核探测技术分会
- 学会名称：中国电子学会核电子学与核探测技术分会
- 页数：6
- 文件大小：636k
- 原文格式：D
- 会议级别：全国
摘要
根据国际热核聚变实验堆ITER设计标准,ITER极向场线圈(PF Coils)的人工检测和连接维修任务的制定,需要开展维修方案的预评估,验证当前核设计方案的合理性和可行性。基于ITER组织提供的辐射场数据和工程模型,在核与辐射安全仿真系统RVIS2.3的支持下,开展了ITER PF4维修过程的工人职业照射剂量仿真分析,包括维修过程的虚拟漫游仿真、器官剂量实时评估、累积剂量评估和人员操作过程的虚拟培训仿真。结果表明,根据现有ITER核设计方案,ITER停堆10~6秒后人员进入低温室开展ITER PF4检修工作所受到的最大辐射剂量率达到了304.4μSv/hr,累积剂量为2.19mSv,最大个人辐射剂量超过了ITER设计标准,建议后续采用临时屏蔽或者推迟工人进入时间降低辐射剂量。
To bridge the failed ITER PF coils double pancake, hands-on access was required for the inspection and installation in cryostat. As the activated component in cryostat would induce radiation hazard, assessing the decay gamma dose rate inside cryostat was needed to determine and schedule personal accessibility to perform the repair. This paper presented the application of virtual reality technology in radiation dose assessment during ITER PF4 coils maintenance. Real-time assessment of workers' exposure dose rate, virtual training of manual inspection and repair, visualization of radiation map and radiation dose reduction study during ITER PF4 coils maintenance have been presented. The results of this simulation suggested that virtual reality technology was a useful method in real-time dose assessment and operator training, the temporary shielding and extending cooling time should be used as radiation dose reduction.
To bridge the failed ITER PF coils double pancake, hands-on access was required for the inspection and installation in cryostat. As the activated component in cryostat would induce radiation hazard, assessing the decay gamma dose rate inside cryostat was needed to determine and schedule personal accessibility to perform the repair. This paper presented the application of virtual reality technology in radiation dose assessment during ITER PF4 coils maintenance. Real-time assessment of workers' exposure dose rate, virtual training of manual inspection and repair, visualization of radiation map and radiation dose reduction study during ITER PF4 coils maintenance have been presented. The results of this simulation suggested that virtual reality technology was a useful method in real-time dose assessment and operator training, the temporary shielding and extending cooling time should be used as radiation dose reduction.
引文
[1]http://www.iter.org
[2]吴宜灿,胡丽琴,龙鹏程等.先进核能软件发展与核信息学实践.中国科研信息化蓝皮书2013,北京:科学出版社,ISBN978-7-03-039323-4,2013.12:232-244.
[3]吴宜灿,胡丽琴,龙鹏程等.先进核能系统设计分析软件与数据库研发进展[J].核科学与工程,2010,30(1).
[4]吴宜灿,李静惊,李莹等.大型集成多功能中子学计算与分析系统Visual BUS的研究与发展.核科学与工程,2007,27(4):365-373.
[5]Pengcheng LONG,Qin ZENG,Tao HE,et.al.Development of a Geometry-Coupled Visual Analysis System for MCNP,Progress in Nuclear Science and Technology,Vol.2,pp.280-283(2011).
[6]Tao He,Pengcheng Long,Shaoheng Zhou,et al.A Method for 3D Structured data sets Regulation Based on Image.Recent Advances in Computer Science and Information Engineering Lecture Notes in Electrical Engineering,Volume 126,2012,pp 643-648.
[7]Zhengdao Tang,Pengcheng Long,Shanqing Huang,et al.Real-time dose assessment and visualization of radiation field for EAST tokamak[J].Fusion Engineering and Design,2010,85(7-9):1591-1594.
[8]ITER IDM:PD-ITER Plant Description2X6K67_v1_1.
[9]http://www.autodesk.com/products/autodesk-3dsmax/overview
[10]M.Z.Youssef,and R.E.Feder.Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code.Fusion Engineering and Design,87(7-8)(2012):1101-1110
[11]Mengyun Cheng,Qin Zeng,Ruifen Cao,Gui Li,Huaqing Zheng,Shanqing Huang,Gang Song,Yican Wu,and FDS Team,Construction a Voxel Model with physical properties derived from the CT numbers,Progress in Nuclear Science and Technology(PNST).2012.
[12]http://www.fds.org.cn
[13]Y.Wu,FDS Team.Conceptual Design of the China Fusion Power Plant FDS-II.Fusion Engineering and Design,2008,83(10-12):1683-1689.
[14]Y.Wu,Y.Bai,W.Wang,et.al,Overview of China Lead Alloy cooled Reactor Development and ADS Program in China,NUTHOS-9,Kaohsiung,Taiwan,September 9-13,2012.
[15]吴宜灿,黄群英,朱志强,等。中国系列液态锂铅实验回路设计与研发进展.核科学与工程,2009,29(2):163-171.
[16]Y.Wu,FDS Team.Conceptual Design Activities of FDS Series Fusion Power Plants in China.Fusion Engineering and Design,2006,81(23-24):2713-2718.
[17].L.Qiu,Y.Wu,B.Xiao,et al.A Low Aspect Ratio Tokamak Transmutation System.Nuclear Fusion,2000,40:629-633.
[18]Y.Wu,FDS Team.CAD-based Interface Programs for Fusion Neutron Transport Simulation.Fusion Engineering and Design,2009,84(7-11):1987-1992.
[19]Y.Li,L.Lu,A.Ding,et al.Benchmarking of MCAM4.0 with the ITER 3D Model.Fusion Engineering and Design,2007,82:2861-2866.
[20]H.Hu,Y.Wu,M.Chen,et al.Benchmarking of SNAM with the ITER 3D Model,Fusion Engineering and Design,82(2007)2867-2871.
[21]Y.C.Wu,Z.S.Xie,U.Fischer.A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Numerical Calculation in Curvilinear Geometries[J].Nuclear Science and Engineering,1999,133:350-357.
[22]Q.Zeng,L.Lu,A.Ding,et al.Update of ITER3D Basic Neutronics Model with MCAM.Fusion Engineering and Design,2006,81(23-24):2773-2778.
[23]ITER IDM:Project Requirements(PR)27ZRW8_v4_6
[2]吴宜灿,胡丽琴,龙鹏程等.先进核能软件发展与核信息学实践.中国科研信息化蓝皮书2013,北京:科学出版社,ISBN978-7-03-039323-4,2013.12:232-244.
[3]吴宜灿,胡丽琴,龙鹏程等.先进核能系统设计分析软件与数据库研发进展[J].核科学与工程,2010,30(1).
[4]吴宜灿,李静惊,李莹等.大型集成多功能中子学计算与分析系统Visual BUS的研究与发展.核科学与工程,2007,27(4):365-373.
[5]Pengcheng LONG,Qin ZENG,Tao HE,et.al.Development of a Geometry-Coupled Visual Analysis System for MCNP,Progress in Nuclear Science and Technology,Vol.2,pp.280-283(2011).
[6]Tao He,Pengcheng Long,Shaoheng Zhou,et al.A Method for 3D Structured data sets Regulation Based on Image.Recent Advances in Computer Science and Information Engineering Lecture Notes in Electrical Engineering,Volume 126,2012,pp 643-648.
[7]Zhengdao Tang,Pengcheng Long,Shanqing Huang,et al.Real-time dose assessment and visualization of radiation field for EAST tokamak[J].Fusion Engineering and Design,2010,85(7-9):1591-1594.
[8]ITER IDM:PD-ITER Plant Description2X6K67_v1_1.
[9]http://www.autodesk.com/products/autodesk-3dsmax/overview
[10]M.Z.Youssef,and R.E.Feder.Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code.Fusion Engineering and Design,87(7-8)(2012):1101-1110
[11]Mengyun Cheng,Qin Zeng,Ruifen Cao,Gui Li,Huaqing Zheng,Shanqing Huang,Gang Song,Yican Wu,and FDS Team,Construction a Voxel Model with physical properties derived from the CT numbers,Progress in Nuclear Science and Technology(PNST).2012.
[12]http://www.fds.org.cn
[13]Y.Wu,FDS Team.Conceptual Design of the China Fusion Power Plant FDS-II.Fusion Engineering and Design,2008,83(10-12):1683-1689.
[14]Y.Wu,Y.Bai,W.Wang,et.al,Overview of China Lead Alloy cooled Reactor Development and ADS Program in China,NUTHOS-9,Kaohsiung,Taiwan,September 9-13,2012.
[15]吴宜灿,黄群英,朱志强,等。中国系列液态锂铅实验回路设计与研发进展.核科学与工程,2009,29(2):163-171.
[16]Y.Wu,FDS Team.Conceptual Design Activities of FDS Series Fusion Power Plants in China.Fusion Engineering and Design,2006,81(23-24):2713-2718.
[17].L.Qiu,Y.Wu,B.Xiao,et al.A Low Aspect Ratio Tokamak Transmutation System.Nuclear Fusion,2000,40:629-633.
[18]Y.Wu,FDS Team.CAD-based Interface Programs for Fusion Neutron Transport Simulation.Fusion Engineering and Design,2009,84(7-11):1987-1992.
[19]Y.Li,L.Lu,A.Ding,et al.Benchmarking of MCAM4.0 with the ITER 3D Model.Fusion Engineering and Design,2007,82:2861-2866.
[20]H.Hu,Y.Wu,M.Chen,et al.Benchmarking of SNAM with the ITER 3D Model,Fusion Engineering and Design,82(2007)2867-2871.
[21]Y.C.Wu,Z.S.Xie,U.Fischer.A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Numerical Calculation in Curvilinear Geometries[J].Nuclear Science and Engineering,1999,133:350-357.
[22]Q.Zeng,L.Lu,A.Ding,et al.Update of ITER3D Basic Neutronics Model with MCAM.Fusion Engineering and Design,2006,81(23-24):2773-2778.
[23]ITER IDM:Project Requirements(PR)27ZRW8_v4_6