高温气冷堆球形燃料元件基体石墨抗氧化性能研究进展
详细信息 查看官网全文
- 英文论文题名：The research progress in oxidation resistant property of HTGR spherical fuel element matrix graphite
- 论文作者：张凯红 ; 周平 ; 赵宏生 ; 李自强 ; 刘小雪 ; 唐春和
- 英文论文作者：ZHANG Kai-hong ; ZHOU Ping ; ZHAO Hong-sheng ; LI Zi-qiang ; LIU Xiao-xue ; TANG Chun-he ; Institute of Nuclear and New Energy Technology of Tsinghua University ; Collaborative Innovation Center of Advanced Nuclear Energy Technology
- 年：2015
- 作者机构：清华大学核能与新能源技术研究院先进核能技术协同创新中心;
- 论文关键词：高温气冷堆 ; 球形燃料元件 ; 基体石墨 ; 抗氧化性能
- 英文论文关键词：high temperature gas cooled reactor ; fuel elements ; matrix graphite ; oxidation resistance
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第5册（核材料分卷、辐射防护分卷）
- 语种：中文
- 分类号：TL424
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：6
- 文件大小：364k
- 原文格式：O
- 会议级别：全国
摘要
高温气冷堆球形燃料元件为球形包覆的UO_2颗粒弥散在燃料区的石墨基体中,基体石墨作为球形燃料元件的第二道安全屏障,既是结构材料,同时也具有提供热工水力学条件、慢化中子和滞留裂变产物的作用。在发生进水和进空气事故工况下,水和氧气可能会不同程度地进入堆芯,引起基体石墨的氧化,因此提高球形燃料元件基体石墨抗氧化性能对高温气冷堆的安全运行和未来发展至关重要。本文综述了国内外核反应堆用石墨材料抗氧化性能方面的研究现状,特别是针对高温气冷堆用基体石墨,以及SiC、SiO_2和SiC/SiO_2涂层涂覆的基体石墨在高氧分压、低氧分压状态下的氧化行为进行了综合评述,并在此基础上提出了改善高温气冷堆球形燃料元件基体石墨抗氧化性能的研究方向。
The high temperature gas-cooled reactor fuel element has spherical structure with coated-UO_2 particles dispersing in the graphite matrix of the fuel area.As the second security barrier of the spherical fuel element,the matrix graphite is not only structural material,but also plays an important role in providing thermal hydraulics,slowing down neutrons and preventing fission products etc.However,water and air may go into the reactor core in the accident operating conditions which will greatly accelerate the oxidation of the matrix graphite,so it is very important to improve the oxidation resistance of the spherical fuel element matrix graphite especially for the safe operating and future development of the HTGR.This paper reviewed the research progress in oxidation resistant behavior of nuclear reactor graphite material home and abroad,especially for the oxidation resistance behavior of HTGR matrix graphite,as well as SiC,SiO_2 and SiC/SiO_2 coated matrix graphite material under different conditions,such as high oxygen partial pressure,low oxygen partial pressure etc.On the basis of this,the research direction of the improvement on the spherical fuel element matrix graphite oxidation resistance has been pointed out.
The high temperature gas-cooled reactor fuel element has spherical structure with coated-UO_2 particles dispersing in the graphite matrix of the fuel area.As the second security barrier of the spherical fuel element,the matrix graphite is not only structural material,but also plays an important role in providing thermal hydraulics,slowing down neutrons and preventing fission products etc.However,water and air may go into the reactor core in the accident operating conditions which will greatly accelerate the oxidation of the matrix graphite,so it is very important to improve the oxidation resistance of the spherical fuel element matrix graphite especially for the safe operating and future development of the HTGR.This paper reviewed the research progress in oxidation resistant behavior of nuclear reactor graphite material home and abroad,especially for the oxidation resistance behavior of HTGR matrix graphite,as well as SiC,SiO_2 and SiC/SiO_2 coated matrix graphite material under different conditions,such as high oxygen partial pressure,low oxygen partial pressure etc.On the basis of this,the research direction of the improvement on the spherical fuel element matrix graphite oxidation resistance has been pointed out.
引文
[1]唐春和.高温气冷堆燃料元件[M].北京:化学工业出版社,2007.
[2]唐春和.HTR-10燃料元件的制造和发展趋势[J].核标准计量与质量,2006,(03):2-12.
[3]雒晓卫,喻新利,于溯源.高温气冷堆用石墨材料的氧化性能研究[J].核动力工程,2007,(05):50-53.
[4]周湘文,易子龙,卢振明,等.球床式高温气冷堆堆内的石墨材料[J].炭素技术,2012,(06):52-56.
[5]朱庆山,邱学良,马昌文.HTR-10球形燃料元件基体石墨抗氧化研究[J].高技术通讯,1998,(03):53-56..
[6]周家斌,付志强,唐春和,等.SiC/SiO_2抗氧化涂层的热稳定性分析[J],失效分析与预防,2007,11(2):6-9
[7]Luo X W,Rob in J C,Yu S Y.E ffect of temp erature on graph iteoxidat ion behavior[J].Nu clea r Eng ineering and D esign,2004,227:273-280.
[8]雒晓卫,于溯源.反应堆用石墨材料的氧化[J].原子能科学技术,2007,41(6):694-698
[9]李贺军,曾燮榕,朱小旗,等.炭/炭复合材料抗氧化研究[J].炭素技术,1999,(3):2-7
[10]杨海峰,王惠,冉新权.C/C复合材料的高温抗氧化研究进展[J].炭素技术,2000,(6):22-28.
[11]Schroder B,Alkan Z,Pott G.Research on SiC-coatingsfor graphite surface in HTR's[J].NEA Workshop on High Temperature Engineering Facilities and Experiment.ECN-Petten,1997.
[12]Hurtado A M,Schroder B,Gottaut H.Ceramic coatings for HTR graphite structures[J].IAEA-TCM Response of fuel,fuel element and gas-cooled reactor cores under accidental air and water ingress conditions.Beijing,1993.
[13]Knorr J,Kerber A,Moormann R.Upgrading(V)HTR fuel elements for generation IV goals by SiC encapsulation[J].Kerntechnik[0932-3902]Knorr,2012,(77):351-355.
[14]Fu ZQ,Wang C,Tang CH,et al.Oxidation behaviors of SiO_2/SiC coated matrix graphite of high temperature gas-cooled reactor fuel element[J].Nuclear Engineering and Design,2013,(265):867-871.
[15]Hongsheng Z,Zhiqiang F,Chunhe T,et al.Study of SiC/SiO_2 oxidation-resistant coatings on matrix graphite for HTR fuel element[J].Nuclear Engineering and Design,2014,(271):217-220.
[16]付志强,唐春和,梁彤祥,等.SiC涂层对高温气冷堆用石墨摩擦磨损性能的影响[J].金属热处理,2005,(09):13-16.
[17]付志强,唐春和,梁彤祥.化学气相沉积法制备SiC/SiO_2梯度复合涂层的热力学分析[J].材料工程,2008,(06):68-71.
[18]李贺军,曾燮榕,朱小旗,等.炭/炭复合材料抗氧化研究[J].炭素技术,1999,(3):2-7.
[19]常春,陈传忠,孙文成.SiC的高温抗氧化性分析[J].山东大学学报,2002,32(6):581-585
[20]SiC涂层性能与石墨基体结构的关系[J].原子能科学技术,2008,42(4):353-356
[2]唐春和.HTR-10燃料元件的制造和发展趋势[J].核标准计量与质量,2006,(03):2-12.
[3]雒晓卫,喻新利,于溯源.高温气冷堆用石墨材料的氧化性能研究[J].核动力工程,2007,(05):50-53.
[4]周湘文,易子龙,卢振明,等.球床式高温气冷堆堆内的石墨材料[J].炭素技术,2012,(06):52-56.
[5]朱庆山,邱学良,马昌文.HTR-10球形燃料元件基体石墨抗氧化研究[J].高技术通讯,1998,(03):53-56..
[6]周家斌,付志强,唐春和,等.SiC/SiO_2抗氧化涂层的热稳定性分析[J],失效分析与预防,2007,11(2):6-9
[7]Luo X W,Rob in J C,Yu S Y.E ffect of temp erature on graph iteoxidat ion behavior[J].Nu clea r Eng ineering and D esign,2004,227:273-280.
[8]雒晓卫,于溯源.反应堆用石墨材料的氧化[J].原子能科学技术,2007,41(6):694-698
[9]李贺军,曾燮榕,朱小旗,等.炭/炭复合材料抗氧化研究[J].炭素技术,1999,(3):2-7
[10]杨海峰,王惠,冉新权.C/C复合材料的高温抗氧化研究进展[J].炭素技术,2000,(6):22-28.
[11]Schroder B,Alkan Z,Pott G.Research on SiC-coatingsfor graphite surface in HTR's[J].NEA Workshop on High Temperature Engineering Facilities and Experiment.ECN-Petten,1997.
[12]Hurtado A M,Schroder B,Gottaut H.Ceramic coatings for HTR graphite structures[J].IAEA-TCM Response of fuel,fuel element and gas-cooled reactor cores under accidental air and water ingress conditions.Beijing,1993.
[13]Knorr J,Kerber A,Moormann R.Upgrading(V)HTR fuel elements for generation IV goals by SiC encapsulation[J].Kerntechnik[0932-3902]Knorr,2012,(77):351-355.
[14]Fu ZQ,Wang C,Tang CH,et al.Oxidation behaviors of SiO_2/SiC coated matrix graphite of high temperature gas-cooled reactor fuel element[J].Nuclear Engineering and Design,2013,(265):867-871.
[15]Hongsheng Z,Zhiqiang F,Chunhe T,et al.Study of SiC/SiO_2 oxidation-resistant coatings on matrix graphite for HTR fuel element[J].Nuclear Engineering and Design,2014,(271):217-220.
[16]付志强,唐春和,梁彤祥,等.SiC涂层对高温气冷堆用石墨摩擦磨损性能的影响[J].金属热处理,2005,(09):13-16.
[17]付志强,唐春和,梁彤祥.化学气相沉积法制备SiC/SiO_2梯度复合涂层的热力学分析[J].材料工程,2008,(06):68-71.
[18]李贺军,曾燮榕,朱小旗,等.炭/炭复合材料抗氧化研究[J].炭素技术,1999,(3):2-7.
[19]常春,陈传忠,孙文成.SiC的高温抗氧化性分析[J].山东大学学报,2002,32(6):581-585
[20]SiC涂层性能与石墨基体结构的关系[J].原子能科学技术,2008,42(4):353-356