Structural integrity assessment of a nuclear vessel with FITNET FFS and Master Curve approach

被引:6
作者
Ferreno, D. [1 ]
Lacalle, R. [1 ]
Cicero, R.
Scibetta, M. [3 ]
Gorrochategui, I. [2 ]
van Walle, E. [3 ]
Gutierrez-Solana, F. [1 ]
机构
[1] Univ Cantabria, ETS Ingenieros Caminos, E-39005 Santander, Spain
[2] Univ Cantabria, ETS Ingenieros Ind & Telecomunicac, CDTUC, CTC, E-39005 Santander, Spain
[3] CEN SCK, B-2400 Mol, Belgium
关键词
Master Curve; Structural integrity; Nuclear vessel; FITNET FFS;
D O I
10.1016/j.engfailanal.2009.06.007
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The structural integrity of a Spanish nuclear vessel was assessed by obtaining the operation pressure-temperature (P-T) limit curves relevant to the beltline region according to the ASME Code. This method requires the knowledge of the material fracture toughness in the ductile to brittle transition (DBT) region which is conventionally described by the semi-empirical reference temperature RT(NDT). Recent development of the Master Curve (MC) methodology, with To as a reference temperature, is an attractive alternative that do not rely on empirical correlations. Thus, the P-T curves were also calculated according to the N-629 and N-631 ASME Code Cases which partially include T(o) through RT(To). Finally, to evaluate the conservatism of the different methodologies (ASME Code and Code Cases), the analysis was performed by means of the FITNET FFS procedure that consistently incorporates the MC concepts. The study demonstrates the conservatism of the ASME code which is manly due to the definition of the semi-empirical RT(NDT) index. (C) 2009 Elsevier Ltd. All rights reserved.
引用
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页码:259 / 269
页数:11
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