The mechanical properties and microstructures of tube sheet of steam generator for the small modular reactor use are estimated to examine the uniformity of material in different sections. The composition analysis shows that the C content varies between 0.18wt.%-0.19wt.%, and S and P contents are less than 0.002 wt.% and 0.005 wt.%, respectively. The contents of other alloying elements vary in a very small and reasonable range. The strength at room (23℃) or elevated temperatures (350℃) is generally homogenously distributed in circumferential direction after quench-temper treatment, whereas the corresponding impact toughness has a relatively larger fluctuation with the average and minimum adsorbed energy of 76 J and 47 J for sample E tested at -10℃, which just meets the required value. The uniformly distributed short rod-like carbides in tempered martensite are responded for the improved combination of strength and toughness, whereas the unevenly distributed carbides with irregular shape at grain boundaries formed due to insufficient hardenability induces unexpected mechanical properties, especially the degraded toughness. Generally, the uniform mechanical properties can be achieved throughout the integral forged tube sheet of steam generator, but it seems that the integral forging and heat treatment processing can be further modified after more meticulous consideration on heat treatments.
ZHANG Lefu
,
MA Wujiang
,
HE Long
,
ZHANG Hao
,
WANG Yuanhua
,
DENG Song
,
LIU Qingdong
. On the Homogeneity of Microstructure and Mechanical Properties for Stream Generator Tube Sheet[J]. Journal of Mechanical Engineering, 2018
, 54(10)
: 103
-109
.
DOI: 10.3901/JME.2018.10.103
[1] 陈培培,周赞. 我国发展先进小型轻刊反应堆的一些思考[J]. 中国核电,2012,5(1):88-93. CHEN Peipei,ZHOU Zan. Recommendations for small water reactor development in China[J]. China Nuclear Power,2012,5(1):88-93.
[2] 陈文军,姜胜耀. 中国发展小型堆核能系统的可行性研究[J]. 核动力工程,2013,34(2):153-156. CHEN Wenjun,JIANG Shengyao. Feasibility study on development of small nuclear power reactors in China[J]. Nuclear Power Engineering,2013,34(2):153-156.
[3] ZHANG Zuoyi,SUN Yuliang. Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project[J]. Nuclear Engineering and Design,2007,237(23):2265-2274.
[4] VUJIĆ J,BERGMANN R M.,ŠKODA R,et al. Small modular reactors:Simpler,safer,cheaper?[J]. Energy,2012,45(1):288-295.
[5] LIU Zhitao,FAN Jihong. Technology readiness assessment of small modular reactor (SMR) designs[J]. Progress in Nuclear Energy,2014,70:20-28.
[6] 熊厚华,杜继富,曾正魁,等. 模块式小型反应堆研发现状及前景分析[J]. 价值工程,2015(2):30-31. XIONG Houhua,DU Jifu,ZENG Zhengkui,et al. Research and development status and prospect analysis of modular miniature nuclear power reactor[J]. Value Engineering,2015(2):30-31.
[7] INGERSOLL D T,HOUGHTON Z J,BROMM R,et al. NuScale small modular reactor for co-generation of electricity and water[J]. Desalination,2014,340(1):84-93.
[8] 潘金生,仝健民,田民波. 材料科学基础[M]. 北京:清华大学出版社,1998. PAN Jinsheng,GONG Jianmin,TIAN Minbo. Fundamentals of material science[M]. Beijing:Tsinghua University Press,1998.
[9] SPEICH G R,LESLIE W C. Tempering of steel[J]. Metallurgical Transactions,1972,3(5):1043-1054.
[10] 刘庆冬,刘文庆,王泽民,等. 回火马氏体中合金碳化物3D原子探针表征Ⅰ形核[J]. 金属学报,2009,45(11):1281-1287. LIU Qingdong,LIU Wenqing,WANG Zemin,et al. 3D atom probe characterization of alloy carbides in tempering martenite I. nucleation[J]. Acta Metallurgica Sinica,2009,45(11):1281-1287.
[11] 刘庆冬,彭剑超,刘文庆,等. 回火马氏体中合金碳化物3D原子探针表征Ⅱ长大[J]. 金属学报,2009,45(11):1288-1296. LIU Qingdong,PENG Jianchao,LIU Wenqing,et al. 3D atom probe characterization of alloy carbides in tempering martenite I. growth[J]. Acta Metallurgica Sinica,2009,45(11):1288-1296.
[12] YAN Guanghua,HAN Lizhan,LI Chuanwei,et al. Characteristic of retained austenite decomposition during tempering and its effect on impact toughness in SA508 Gr.3 steel[J]. Journal of Nuclear Materials,2017,483:167-175.
[13] LIU Qingdong,LIU Wenqing,XIONG Xiangyuan. Correlation of Cu precipitation with austenite-ferrite transformation in a continuously cooled multicomponent steel:An atom probe tomography study[J]. Journal of Materials Research,2012,27(7):1060-1067.
[14] AHN Y S,KIM H D,BYUN T S,et al. Application of intercritical heat treatment to improve toughness of SA508 Cl.3 reactor pressure vessel steel[J]. Nuclear Engineer Design,1999,194(2-3):161-177.
