Assessment of the WWER-1000 reactor condition

被引:10
|
作者
Timofeev, B. T. [1 ]
Karzov, G. P. [1 ]
机构
[1] CRISM Prometey, St Petersburg 191015, Russia
关键词
reactor pressure vessel; design; shell; mechanical properties; statistical treatment;
D O I
10.1016/j.ijpvp.2005.11.008
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The current state of the materials (steel, welds, anticorrosive cladding metal) of WWER-1000 RPVs has been examined, taking into consideration special features of their manufacture and operation for 30 years. The possibility of operating these reactors after their design service life has been estimated, allowing for the degradation of properties due to thermal and radiation influence, as well as damage from cyclic loads. Life extension has been shown to be possible but will require future analysis of the state of the material at the end of the design life. (c) 2006 Elsevier Ltd. All rights reserved.
引用
收藏
页码:464 / 473
页数:10
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