%0 Journal Article
%T STRESS CORROSION CRACKING OF ENGINEERING MATERIALS USED IN NUCLEAR POWER PLANTS<br>核电工程材料的应力腐蚀破裂研究
%A YANG Wu
%A <br>杨武
%J 腐蚀科学与防护技术
%D 1995
%I 
%X The effects of impurity ions, dissolved oxygen, applied potential and temperature onstress corrosion cracking (SCC) of engineering materials used in nuclear power plants, including304 stainless steel (SS), 316 SS and A533B pressure vessel steel, in high temperature water havebeen investigated using slow strain rate testing (SSRT) and U--bend testing techniques, comple'mented by electrochemical measurements and Auger electron spectroscopy (AES) analyses of thesurface films formed on specimens. A suggestion for choosing the accelerating testing methods isproposed based on the comparison of the results of SSRT and U--bends. This paper briefly introduces some most important results.
%K engineering materials
%K nuclear power plant
%K stress corrosion cracking
%K high temperature water
%K slow strain rate test
%K U--bend
%K surface film<br>工程材料
%K 应力腐蚀破裂
%K 核电站
%K 弯曲试验
%K 反应堆
%U http://www.alljournals.cn/get_abstract_url.aspx?pcid=5B3AB970F71A803DEACDC0559115BFCF0A068CD97DD29835&cid=AB188D3B70B071C57EB64E395D864ECE&jid=9F6E6EC8BA5BB62698F6640073DDD6E1&aid=81BC2EAB17D31272526DF4DED991A24D&yid=BBCD5003575B2B5F&vid=DF92D298D3FF1E6E&iid=0B39A22176CE99FB&sid=117F81797AB182FC&eid=08805F9252973BA4&journal_id=1002-6495&journal_name=腐蚀科学与防护技术&referenced_num=2&reference_num=0