黄群英,女,博士,中科院合肥物质科学研究院研究员、博士生导师,研究所副总工。
人物经历
2009年起任先后任反应堆技术研究室主任、先进反应堆技术与材料中心主任、中科院合肥物质科学研究院学术委员会委员。
2006年获中国科学院合肥物质科学研究院核能科学与工程专业博士学位。
2004年赴东京大学做客座教授,
1998年和2002年,分别赴英国Culham科学中心和日本国立聚变科学研究所(NIFS)做访问学者
1986年、1989年先后获西安交通大学核反应堆工程与安全专业学士学位与硕士学位
科研项目
目前主持先进反应堆结构材料中国低活化
马氏体钢研发、先进堆液态重金属回路研发及相关实验研究等相关工作。研发的反应堆物理计算软件通过
国家核安全局成果鉴定,被大亚湾、秦山等多家核电站和核动力第一设计院等单位广泛应用于实际反应堆的物理设计与分析中。
科研成果
公开发表学术论文150余篇,相关论文先后多次入选“中国百篇最具影响国内学术论文”、“第五届中国科协期刊优秀学术论文奖”、多篇论文入选“ESI高被引论文”。获授权专利70余项。
获得荣誉
成果先后获国家自然科学二等奖、国家科技进步三等奖、国家能源科技进步一等奖、中国核能行业协会科学技术奖一等奖、国家教委科技进步一等奖、安徽省科技进步一等奖(自然科学类)、西安交通大学科技成果二等奖、院级/所级成果多项。获安徽省省直机关“优秀女性”、“
三八红旗手”称号;被评为中国科学院“朱李月华优秀教师”、中国科学院合肥物质科学研究院“优秀研究生导师”。
研究方向
1、先进反应堆设计
2、反应堆材料及堆关键技术研发
3、反应堆物理与屏蔽设计及其先进计算方法
论文专著
(1) Status and improvement of CLAM for nuclear application - Nuclear Fusion - 2017 - 57
(2) Recent progress of R&D activities on reduced activation ferritic_martensitic steels - Journal of Nuclear Materials - 2013 - 442
(3) Progress in Development of CLAM Steel and Fabrication of Small TBM in China - Journal of Nuclear Materials - 2011 - 417
(4) Development status of CLAM steel for fusion application - Journal of Nuclear Materials - 2014 - 445
(5) Progress in compatibility experiments on lithium–lead with candidate structural materials for fusion in China - Fusion Engineering and Design - 2009 - 84
(6) Effect of Surface Preparation on CLAM/CLAM Hot Isostatic Pressing diffusion bonding joints - Journal of Nuclear Materials - 2009 - 386-388
(7) Effect of post-weld heat treatment on the mechanical properties of electron beam welded joints for CLAM steel - Journal of Nuclear Materials - 2013 - 442
(8) Creep deformation and rupture behavior of CLAM steel at 823 K and 873 K - Journal of Nuclear Materials - 2014 - 455
(9) Swelling of CLAM steel irradiated by electron/helium to 17.5 dpa with 10 appm He/dpa - Fusion Engineering and Design - 2011 - 86
(10) Corrosion behavior of CLAM steel in static and flowing LiPb at 480 °C and 550 °C - Fusion Engineering and Design - 2011 - 86
(11) Status and Strategy of Fusion Materials Development in China - Journal of Nuclear Materials - 2009 - 386-388
(12) Mechanical Properties and Microstructures of China Low Activation Martensitic Steel Compared with JLF-1 - Journal of Nuclear Materials - 2007 - 367-370
(13) Effects of Addition of Yttrium on Properties and Microstructure for China Low Activation Martensitic Steel (CLAM) - Fusion Engineering and Design - 2007 - 82
(14) Preliminary analysis of irradiation effects on CLAM after low dose neutron irradiation - Journal of Nuclear Materials - 2009 - 386-388
(15) Comparison of corrosion behavior of EUROFER and CLAM steels in flowing Pb–15.7Li - Journal of Nuclear Materials - 2014 - 445
(16) Mechanical properties and microstructure evolution of CLAM Steel in tube fabrication and test blanket module assembly - Journal of Nuclear Materials - 2013 - 442
(17) Continuous cooling transformation behaviors of CLAM steel - Journal of Nuclear Materials - 2013 - 442
(18) Preliminary study of HDA coating on CLAM steel followed by high temperature oxidation - Journal of Nuclear Materials - 2013 - 442
(19) Corrosion Experiment in the First Liquid Metal LiPb Loop of China - the 24th Symposium on Fusion Technology - 2006 - Sept.11-15
(20) Development strategy and conceptual design of China Lead-based Research Reactor - Annals of Nuclear Energy - 2016 - 87
(21) Progress in development of fabrication of small TBMs for EAST and ITER - Fusion Engineering and Design - 2010 - Vol.85
(22) Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor - Advances in Science and Technology - 2010 - 73
(23) Design and Analysis of DRAGON-IV LiPb Loop - Fusion Engineering and Design - 2011 - 86
(24) Corrosion analysis of CLAM steel in flowing liquid LiPb at 480 oC - Fusion Engineering and Design - 2010 - 85
(25) Preliminary Experimental study on Hot Isostatic Pressing Diffusion Bonding for CLAM-CLAM - the 24th Symposium on Fusion Technology - 2006 - sept.11-15
(26) Effects of Addition of Yttrium on Properties and Microstructure for China Low Activation Martensitic Steel - the 24th Symposium on Fusion Technology - 2006 - Sept.11-15
(27) Small Specimen Test Techniques Applied to Evaluate the Mechanical Properties of CLAM Steel - Journal of Fusion Energy - 2015 - 34
(28) Latest progress on R&D of ITER DFLL-TBM in China - Fusion Engineering and Design - 2011 - 86
(29) Facilities, testing program and modeling needs for studying liquid metal magnetohydrodynamic flows in fusion blankets - Fusion Engineering and Design - 2015 - 100
(30) Tritium Analysis of Fusion-Based Hydrogen Production Reactor FDS-III - Fusion Engineering and Design - 2010 - 85
(31) Study on Welding Techniques of CLAM steel for Test Blanket Module - Fusion Engineering and Design - 2009 - 84
(32) Influence of Non-metal Inclusions on Mechanical Properties of CLAM Steel - Fusion Engineering and Design - 2009 - 84
(33) ITER TBM 包层材料相关问题 - 聚变安全及包层材料研讨会,合肥 - 2006 - 2006.4
(34) 中国低活化马氏体钢CLAM研究进展 - 核科学与工程 - 2007 - 第27卷第1期
(35) CLAM钢冲击和拉伸性能测试与研究 - 原子核物理评论 - 2006 - 第23卷第2
(36) 中国低活化马氏体钢(CLAM)热等静压扩散焊接初步研究 - 核科学与工程 - 2007 - 第27卷第1期
(37) 中国系列液态锂铅实验回路设计与研制进展 - 核科学与工程 - 2009 - 2009年第二期
(38) 聚变堆液态金属锂铅包层多功能涂层研发 - 核科学与工程 - 2008 - 2008年第三期
(39) 中国低活化马氏体钢CLAM在液态锂铅中腐蚀的初步实验研究 - 核科学与工程 - 2007 - 第27卷第1期
(40) 液态铅铋回路设计研制与材料腐蚀实验初步研究 - 核科学与工程 - 2010 - 2010年第三期
学术兼职
国际能源署聚变核技术执行委员会(NTFR)中国液态包层领域负责人;第13届国际聚变堆材料大会(ICFRM-13、ICFRM-15、ICFRM-16)及第9-10届国际聚变核技术大会(ISFNT-9、ISFNT-10)技术委员会委员;中国计算物理学会蒙特卡罗方法专业委员会委员;
国家自然科学基金、中国留学回国基金、青年拔尖人才支持计划等评审专家;Fusion Engineering & Design、Journal of Nuclear Materials、Fusion Science & Technology、Chinese Physics Letters、《
原子能科学技术》、《
核科学与工程》、《
核聚变与等离子体物理》、《计算物理》等期刊特约评审。