The Charpy impact fracture behaviour in ABS materials

Author(s):  
Yanchun Han ◽  
Ralf Lach ◽  
Wolfgang Grellmann
2006 ◽  
Vol 2006 (0) ◽  
pp. 167-168
Author(s):  
Teruyoshi DAITOH ◽  
Go SHIMIZU ◽  
Masashi KANETSUNA ◽  
Ginsuke KONO

2010 ◽  
Vol 41 (1) ◽  
pp. 67-75 ◽  
Author(s):  
Szu-Hui Lim ◽  
Aravind Dasari ◽  
Gong-Tao Wang ◽  
Zhong-Zhen Yu ◽  
Yiu-Wing Mai ◽  
...  

2005 ◽  
Vol 41 (10) ◽  
pp. 386-392
Author(s):  
Satoshi MATSUDA ◽  
Hajime KISHI ◽  
Hiroki TSUJI ◽  
Atsushi MURAKAMI

2020 ◽  
Vol 12 (2) ◽  
pp. 168781402090456
Author(s):  
Guojun Wei ◽  
Chenglong Wang ◽  
Xingwang Yang ◽  
Zhenfeng Tong ◽  
Wenwang Wu

The mechanical performance of reactor pressure vessel materials is an important factor in the safety and economics of the operation of a nuclear power plant. The ductile-to-brittle transition temperature tested by Charpy impact test is the key parameter for evaluating the reactor pressure vessel embrittlement. In this article, the study of thermal aging embrittlement of temperature sets of reactor pressure vessel surveillance Ni-Cr-Mo-V steel weld metal was conducted by Charpy impact test. The thermal aging effect on the impact fracture behavior was analyzed. The impact test of the three batches of weld surveillance sample indicated that the weld metal embrittled during thermal aging. The study of impact fracture and Auger electron spectroscopy indicated that the element P segregated to the grain boundaries and lowered their cohesion strength during the long-term thermal aging. Therefore, the non-hardening embrittlement of Ni-Cr-Mo-V steel welds in a reactor pressure vessel caused by segregation of impurity elements P occurs during thermal aging.


2017 ◽  
Vol 12 (3) ◽  
pp. 16-00267-16-00267
Author(s):  
Kazuhiro FUJISAKI ◽  
Ayumi HASEGAWA ◽  
Hiroya YOKOYAMA ◽  
Kazuhiko SASAGAWA

1995 ◽  
Vol 56 (9) ◽  
pp. 1059-1063 ◽  
Author(s):  
Yanchun Han ◽  
Yuming Yang ◽  
Binyao Li ◽  
Xuhui Wang ◽  
Zhiliu Feng

Sign in / Sign up

Export Citation Format

Share Document