High-fluence irradiation growth of cold-worked Zr-2.5Nb

被引:20
作者
Holt, RA [1 ]
Causey, AR [1 ]
Griffiths, M [1 ]
Ho, ETC [1 ]
机构
[1] AECL Res, Chalk River Labs, Fuel Channels Div, Chalk River, ON K0J 1J0, Canada
来源
ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM | 2000年 / 1354卷
关键词
zirconium alloys; Zr-2.5Nb; pressure tubes; irradiation growth; temperature; neutron fluence; iron; nuclear materials; radiation effects;
D O I
10.1520/STP14296S
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
Irradiation growth specimens manufactured from cold worked Zr-2.5Nb pressure tube material have been irradiated in Osiris at a fast flux of similar to 1.8 x 10(18) n . m(-2) . s(-1) . E > 1 MeV, at nominal temperatures of 553 and 583 K, to growth strains of 1%. The pressure tubes have a pronounced crystallographic texture, with similar to 95% of the basal plant normals in the radial/transverse plane, predominantly in the transverse direction. Both longitudinal specimens, which generally exhibit positive growth strains, and transverse specimens, which generally exhibit negative strains with approximately 50% of the magnitude of the axial strains, show nonlinear growth, the rate increasing gradually with fluence up to 1.3 X 10(26) n . m(-2), E > 1 MeV (580 K) and 1.7 x 10(26) n . m(-1). E > 1 MeV (550 K). The previously reported temperature dependence of the axial growth strains (decreasing with increasing temperature for fluences up to 4 to 5 x 10(25) n . m(-2), E > 1 MeV) is maintained to the higher fluences now achieved, as is the effect of Fe (axial growth strains decreasing with increased Fe concentration in the range 380-1090 ppm by wt.). The effects of temperature and Fe in the transverse direction an approximately the reverse of those in the longitudinal direction. Examination by transmission electron microscopy and X-ray diffraction of Zr-2.5hrb pressure tubes irradiated to 1 x 10(26) n . m(-2), E > 1 MeV, at 520 to 570 K in power reactors, and fracture toughness specimens machined from pressure tubes and irradiated, unstressed, in Osiris to 1.5 x 10(26) n . m(-2), E > 1 MeV, at 530 R, shows a multiplication of the c-component dislocations with increasing fast fluence. This contracts with a rapid saturation of the density of a-type dislocations after about 0.1 x 10(26) n . m(-2), E > 1 MeV. The multiplication of the c-component dislocations occurs mainly by nucleation of vacancy loops on screw dislocations; this mostly occurs in crystals with their c-axes close to the radial direction because they tend to contain many c-component screw dislocations. Crystals with their c-axes close to the transverse direction contain fewer screw dislocations and exhibit less dislocation multiplication over the fluence range studied. Thus, the gradual evolution of the growth rate with fluence appears to be related to the gradual increase in the c-dislocation density with time as in the case of Zircaloy-2.
引用
收藏
页码:86 / 104
页数:19
相关论文
共 16 条
[1]  
[Anonymous], 1996, ASTM STP 1295
[2]   THE EFFECT OF INTERGRANULAR STRESSES ON THE TEXTURE DEPENDENCE OF IRRADIATION GROWTH IN ZIRCONIUM ALLOYS [J].
CAUSEY, AR ;
WOO, CH ;
HOLT, RA .
JOURNAL OF NUCLEAR MATERIALS, 1988, 159 :225-236
[3]  
Christodoulou N., 1996, ASTM STP, V1295, P518
[4]  
DAVIES PH, 1994, AM SOC TEST MATER, V1245, P135, DOI 10.1520/STP15188S
[5]  
FLECK RG, 1994, AM SOC TEST MATER, V1245, P168, DOI 10.1520/STP15189S
[6]   STUDY OF POINT-DEFECT MOBILITIES IN ZIRCONIUM DURING ELECTRON-IRRADIATION IN A HIGH-VOLTAGE ELECTRON-MICROSCOPE [J].
GRIFFITHS, M ;
STYLES, RC ;
WOO, CH ;
PHILLIPP, F ;
FRANK, W .
JOURNAL OF NUCLEAR MATERIALS, 1994, 208 (03) :324-334
[7]   MICROSTRUCTURAL ASPECTS OF ACCELERATED DEFORMATION OF ZIRCALOY NUCLEAR-REACTOR COMPONENTS DURING SERVICE [J].
GRIFFITHS, M ;
HOLT, RA ;
ROGERSON, A .
JOURNAL OF NUCLEAR MATERIALS, 1995, 225 :245-258
[8]  
Griffiths M., 1989, ASTM STP, V1023, P658
[9]  
Griffiths M., 1991, Adv. X-ray Anal., V35, P593
[10]  
Holt R.A., 1996, ASTM STP, V1295, P623, DOI DOI 10.1520/STP16193S