Analysis method of Charpy V-notch impact data before and after electron beam welding reconstitution

被引:23
作者
Wan Qiang-mao [1 ,2 ]
Wang Rong-shan [1 ]
Shu Guo-gang [2 ,3 ]
Ding Hui [2 ]
Huang Ping [1 ]
Lv Feng [1 ]
Weng Li-kui [1 ]
机构
[1] Suzhou Nucl Power Res Inst, Res Ctr Plant Life Management, Suzhou, Peoples R China
[2] Wuhan Univ, Sch Power & Mech Engn, Dept Mat Engn, Wuhan 430072, Peoples R China
[3] China Nucl Power Enginerring Co Ltd, Shenzhen, Peoples R China
关键词
Charpy V-notch impact (CVN) specimens; Ductile-brittle transition temperature (DBTT); t/t '-Test; Specimen reconstitution technique; Surveillance program;
D O I
10.1016/j.nucengdes.2010.11.005
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The specimen reconstitution technique is one of the most promising techniques to improve the surveillance program of the reactor pressure vessel (RPV). In this study, unirradiated 30Mn2V low-alloy steels were chosen as the test materials, and the broken halves of Charpy V-notch impact (CVN) specimens were reconstituted to be new CVN specimens by the electron beam welding (EBW) as a pilot study in China. Taking the 20 insert reconstituted specimens as an example, Boltzmann function was used to fit the CVN data, the ductile-brittle transition temperature (DBTT) and its uncertainty were evaluated, and the equality of DBTT between the reconstituted specimens and original specimens was checked by t/t'-test. There is a great consistency between CVN data of EBW reconstituted specimens and that of original specimens. (C) 2010 Published by Elsevier B.V.
引用
收藏
页码:459 / 463
页数:5
相关论文
共 19 条
[1]   Neutron embrittlement of VVER reactor pressure vessels -: recent results, open issues and new developments [J].
Ahlstrand, R ;
Bièth, M ;
Rieg, C .
NUCLEAR ENGINEERING AND DESIGN, 2004, 230 (1-3) :267-275
[2]  
*ASTM, 2007, E125307 ASTM
[3]   Validation and application of the Master Curve and reconstitution techniques to a Spanish nuclear vessel [J].
Ferreno, D. ;
Scibetta, M. ;
Gorrochategui, I. ;
Lacalle, R. ;
van Walle, E. ;
Gutierrez-Solana, F. .
ENGINEERING FRACTURE MECHANICS, 2009, 76 (16) :2495-2511
[4]   Survey of national regulatory requirements relevant to PWR pressure vessels [J].
Gérard, R .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1998, 75 (14) :979-1036
[5]  
HENG JH, 2002, STEEL WIRE PRODUCTS, V28, P39
[6]   JAPEIC's activity on aging issue related to neutron irradiation of RPV/RV materials [J].
Kataoka, S ;
Otsuka, T .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2000, 77 (10) :569-574
[7]  
KATAOKA S, 2001, ASTM STP, V1405
[8]  
Keim E., 2002, ASTM STP, V1418
[9]  
ONIZAWA K, 1997, ASTM STP, V1329
[10]  
Petrov P., 2008, WELD WORLD, V52, P365