Evaluation of variables affecting crack propagation by Delayed Hydride Cracking in Zr-2.5Nb with different heat treatments

被引:16
作者
Mieza, J. I. [1 ,2 ]
Vigna, G. L. [1 ]
Domizzi, G. [1 ]
机构
[1] Ctr Atom Constituyentes, CNEA, Bs As, Argentina
[2] UNSAM CNEA, Inst Sabato, Bs As, Argentina
关键词
TERMINAL SOLID SOLUBILITY; ZR-2.5-PERCENT NB ALLOY; ZIRCONIUM ALLOYS; PRESSURE TUBES; TEMPERATURE MODEL; COMBINED SIF; BETA-PHASE; PCT NB; HYDROGEN; MICROSTRUCTURE;
D O I
10.1016/j.jnucmat.2011.01.101
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Delayed Hydride Cracking (DHC) is a failure mechanism that may occur in zirconium alloys used in nuclear reactor core components. The knowledge of the direct effects of the variables affecting the cracking velocity could be used to minimize the risk of crack propagation. In practice, most of these variables as for example the alloy yield stress and hydrogen diffusion coefficient - are coupled and vary during reactor operation, leading to a complex variable dependence of the cracking mechanism. In order to get an insight into the relative effect of these variables, experimental data and a theoretical approach using a generally accepted DHC model were used in this work. A series of DHC velocity measurements were made in Zr-2.5Nb tube with different heat treatments. The yield stress, the Nb concentration in beta phase, and hydrogen solvus of the alloy were measured for different heat treatments. Niobium concentration in beta phase gave an indirect indication of beta-phase continuity and, with a proper correlation, of the hydrogen diffusion coefficient. The obtained values were used as inputs in a theoretical calculation of cracking velocity. Good agreement between experimental data and predicted values was obtained, showing that hydrogen diffusion coefficient was the most relevant variable affecting DHC velocity cracking. Furthermore, this approach has been demonstrated to be useful in estimating DHC velocity in irradiated materials. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:150 / 159
页数:10
相关论文
共 45 条
[1]   AGE HARDENING OF ZR-2.5 WT PERCENT NB SLOWLY COOLED FROM (ALPHA+BETA) PHASE FIELD [J].
ALDRIDGE, SA ;
CHEADLE, BA .
JOURNAL OF NUCLEAR MATERIALS, 1972, 42 (01) :32-&
[2]  
Ambler J., 1984, ZIRCONIUM NUCL IND 6, P653
[3]   EFFECT OF HEAT-TREATMENT ON DELAYED HYDRIDE CRACKING IN ZR-2.5 WT PCT NB [J].
AMOUZOUVI, KF ;
CLEGG, LJ .
METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1987, 18 (10) :1687-1694
[4]  
[Anonymous], E182008A ASTM
[5]   Structural properties and high-temperature reactions of the metastable Ω phase in Zr-Nb alloys [J].
Aurelio, G ;
Guillermet, AF ;
Cuello, GJ ;
Campo, J .
JOURNAL OF NUCLEAR MATERIALS, 2005, 341 (01) :1-11
[6]   DILATATIONAL MISFIT OF ZIRCONIUM HYDRIDES PRECIPITATED IN ZIRCONIUM [J].
CARPENTER, GJ .
JOURNAL OF NUCLEAR MATERIALS, 1973, 48 (03) :264-266
[7]  
Chow C.K., 1996, ASTM Spec. Tech. Publ, V1295, P469
[8]   Influence of metallurgical variables on delayed hydride cracking in Zr-Nb pressure tubes [J].
Cirimello, P ;
Domizzi, G ;
Haddad, R .
JOURNAL OF NUCLEAR MATERIALS, 2006, 350 (02) :135-146
[9]  
Coleman C.E., 1987, 26 ANN C MET CAN I M
[10]  
Coleman C.E., 1979, REV COATINGS CORROSI, VIII, P105