载荷对HTR-PM高温气冷堆用石墨球摩损性能的影响

辐射防护 ›› 2019, Vol. 39 ›› Issue (6): 510-516.

载荷对HTR-PM高温气冷堆用石墨球摩损性能的影响

邓少刚, 郭丽潇, 梁宇, 张宇航, 梁栋, 王永仙

中国辐射防护研究院,太原 030006

收稿日期:2018-06-12 出版日期:2019-11-20 发布日期:2020-05-15
作者简介:邓少刚(1988—),男, 2011年毕业于贵州大学化学工程与工艺专业,2015年毕业于四川大学化学工程专业,获硕士学位,助理研究员。E-mail: dsg_cirp@163.com
基金资助:
华能集团科技项目(项目编号:HNKJ-H18)。

Effect of loads on wear performance of graphite pebbles used in HTR-PM high temperature gas cooled reactor

DENG Shaogang, GUO Lixiao, LIANG Yu, ZHANG Yuhang, LIANG Dong, WANG Yongxian

China Institute for Radiation Protection, Taiyuan 030006

Received:2018-06-12 Online:2019-11-20 Published:2020-05-15

摘要/Abstract

摘要： 采用摩擦磨损试验机研究了载荷对HTR-PM高温气冷堆用石墨球在氦气气氛下的摩损性能影响,并利用光学显微镜分析了磨损表面形貌,利用激光粒度仪和扫描电镜分析了石墨粉尘的粒度和形貌。结果表明:在氦气气氛下,摩擦系数随着载荷的增加呈现减小的趋势;产生的石墨粉尘主要呈片状或絮状体,有较强的粘附性,粒度随着载荷的增加而增加;不同载荷下,随着时间的增加,石墨球的磨损率不断减小,最终趋于一个稳定值。

关键词: 高温气冷堆, 载荷, 石墨球, 摩损性能

Abstract: Wear performance of graphite pebbles used in the HTR-PM high temperature gas cooled reactor at different loads in helium were investigated with a friction and wear tester. Surface and appearance of graphite pebbles were analyzed using a optical microscope. Particle size and pattern of graphite dust were studied using a scanning electron microscope and laser particle analyzer. Results show that in helium atmosphere, the friction coefficient decreases as the load increases. The graphite dust is mainly flaky or flocculent, and has strong adhesiveness. Particle size of the graphite dust increases as the load increases. At different loads, the wear rate of graphite pebbles decreases continuously and eventually goes to a steady value.

Key words: HTR-PM, load, graphite pebble, wear performance

中图分类号:

TL342

邓少刚, 郭丽潇, 梁宇, 张宇航, 梁栋, 王永仙. 载荷对HTR-PM高温气冷堆用石墨球摩损性能的影响[J]. 辐射防护, 2019, 39(6): 510-516.

DENG Shaogang, GUO Lixiao, LIANG Yu, ZHANG Yuhang, LIANG Dong, WANG Yongxian. Effect of loads on wear performance of graphite pebbles used in HTR-PM high temperature gas cooled reactor[J]. RADIATION PROTECTION, 2019, 39(6): 510-516.

参考文献 11

[1]	Gottaut H, Kruger K. Results of experiments at the AVR reactor[J]. Nuclear Engineering & Design, 1990, 121 (2): 143-153.
[2]	吴宗鑫.我国高温气冷堆的发展[J].核动力工程,2000,21(1):39-43.WU Zongxin. The development of high temperature gas-cooled reactor in China[J]. Nuclear Power Engineering,2000,21(1):39-43.
[3]	Rostamian M. Computational prediction of dust production in graphite moderated pebble bed reactors[J]. Le Progrès Agricole Et Viticole, 2012, 126: 571-581.
[4]	吴宗鑫,张作义.世界核电发展趋势与高温气冷堆[J].核动力工程,2000,20(3):211-219.WU Zongxin, ZHANG Zuoyi. World development of nuclear power system and high temperature gas-cooled reactor[J]. Chinese Journal of Nuclear Science and Engineering, 2000, 20(3):211-219.
[5]	雒晓卫,于溯源,盛选禹,等.IG-11石墨在不同气氛中的磨损性能研究[J].摩擦学学报,2005,25(2):173-177.LUO Xiaowei, YU Suyuan, SHENG Xuanyu, et al. Wear behavior of graphite IG-11 in different gas environments[J]. Tribology, 2005,25(2):173-177.
[6]	雒晓卫,于溯源,盛选禹,等.温度对10 MW高温气冷堆用石墨磨损性能的影响[J].摩擦学学报,2004,24(5):402-405.LUO Xiaowei, YU Suyuan, SHENG Xuanyu, et al. Effect of temperatures on the friction behavior of graphite5 used in a nuclear reactor[J]. Tribology, 2004,24(5):402-405.
[7]	郭丽潇,梁栋,王秀娟,等.高温气冷堆蒸汽发生器中的石墨粉尘沉积[J].中国粉体技术,2019,25(2):47-53.GUO Lixiao, LIANG Dong, WANG Xiujuan, et al. Graphite dust deposition in high temperature gas cooled reactor[J]. China Powder Science And Technology, 2019,25(2):47-53.
[8]	雒晓卫,于溯源,盛选禹,等.高温气冷堆用石墨磨损性能研究[J].原子能科学技术,2004,38(3):226-230.LUO Xiaowei, YU Suyuan, SHENG Xuanyu, et al. Tribological properties difference of various graphite used in 10MW high temperature gas-cooled reactor[J]. Atomic Energy Science and Technology, 2004,38(3):226-230.
[9]	郭仁炳.规则球粒堆积体的孔隙度[J].中国地质大学学报,1994,19(4):503-508.GUO Renbing. Porosity of regular spherulitic accumulation[J].Earth Science——Journal of China University of Geosciences, 1994,19(4):503-508.
[10]	雒晓卫. 10 MW 高温气冷堆中石墨粉尘行为研究[D].北京:清华大学,2004.LUO Xiaowei. Research on graphite dust behavior in 10 MW high temperature gas-cooled reactor[D].Beijing: Tsinghua University,2004.
[11]	梁宇,郭丽潇,邓少刚,等. HTR-PM高温气冷示范堆堆芯石墨粉尘产生量估算[J].辐射防护,2018,38(5):409-413.LIANG Yu, GUO Lixiao, DENG Shaogang, et al. The estimation of the graphite dust production in core of high temperature gas cooled reactor[J]. Radiation Protection, 2018,38(5):409-413.