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Acta Metall Sin  2011, Vol. 47 Issue (9): 1205-1209    DOI: 10.3724/SP.J.1037.2011.00214
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SMALL PUNCH TESTING OF THE EFFECT OF IRRADIATION ON MECHANICAL PROPERTY OF RPV STEEL
ZHONG Weihua, TONG Zhenfeng, ZHANG Changyi, QIAO Jiansheng, YANG Wen
China Institute of Atomic Energy, Beijing 102413
Cite this article: 

ZHONG Weihua TONG Zhenfeng ZHANG Changyi QIAO Jiansheng YANG Wen. SMALL PUNCH TESTING OF THE EFFECT OF IRRADIATION ON MECHANICAL PROPERTY OF RPV STEEL. Acta Metall Sin, 2011, 47(9): 1205-1209.

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Abstract  The small punch (SP) test on mechanical properties of the reactor pressure vessel (RPV) steel (A508-3) before and after irradiation was performed at -150 to 20℃, and then the relation between the tested results and standard test results was analyzed based on the empirical method. SEM analysis on the fractograph was carried out to study the mechanism of fracture under different temperatures. The impact property extracted from SP test on the irradiated specimen was compared with the standard impact test data, the result shows that the SP tested fracture energy can be a good value to character the irradiation hardening and embrittlement of the RPV steel. The tensile values which extracted from the SP test show the irradiation embrittlement effect as well.
Key words:  steel A508-3      reactor pressure vessel      irradiation      small punch      mechanical property     
Received:  06 April 2011     
Fund: 

Supported by National Basic Research Program of China (No.2011CB610503)

URL: 

https://www.ams.org.cn/EN/10.3724/SP.J.1037.2011.00214     OR     https://www.ams.org.cn/EN/Y2011/V47/I9/1205

[1] Mnahan M P, Argon A S, Harling O K. J Nucl Mater, 1981; 103-104: 1545

[2] Huang F H, Hamilton M L, Wire G L. J Nucl Technol, 1982; 57: 234

[3] Manahan M P. J Nucl Technol, 1983; 63: 295

[4] Lucas G E, Sheckherd J W, Odette G R. J Nucl Mater, 1984; 122: 429

[5] Misawa T, Adachi T, Satto M, Hamaguchi Y. J Nucl Mater, 1987; 212: 202

[6] Kameda J, Mao X. J Mater Sci, 1992; 27: 983

[7] Foulds J R, Viswanathan R. J Eng Mater Technol, 1994; 116: 457

[8] Ha J S, Fleury E. Int J Press Vessel Pip, 1998; 75: 707

[9] Bulloch J H. Eng Fail Analy, 2004; 11: 635

[10] Jia X J, Dai Y. J Nucl Mater, 2003; 323: 360

[11] Han H, Wang Z W, Guang K S. Press Vessel Technol, 2004; 21(10): 14

(韩浩, 王志文, 关凯书. 压力容器, 2004; 21(10): 14)

[12] Hui H, Han H,Wang ZW, Li P N. Press Vessel Technol, 2009; 26(1): 1

(惠虎, 韩浩, 王志文, 李培宁. 压力容器, 2009; 26(1): 1)

[13] Wang Z X, Shi H J, Lu J, Shi P, Ma X F. J Nucl Eng Des, 2008; 238: 3186

[14] Ding K Q, Shou B N, Wu Y L. J Exp Mech, 2008; 23(6): 539

(丁克勤, 寿比南, 吴永礼. 实验力学, 2008; 23(6): 539)

[15] Finarelli D, Carsughi F, Jung P. J Nucl Mater, 2008; 337: 65
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