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

被引:19
|
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
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 50 条
  • [31] EFFECTS OF TEMPERATURE AND NEUTRON FLUENCE ON IRRADIATION GROWTH OF ZR-2.5 WT-PERCENT NB
    FLECK, RG
    HOLT, RA
    PEROVIC, V
    TADROS, J
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1988, 159 : 75 - 85
  • [32] HYDROGEN INGRESS INTO OXIDIZED ZR-2.5NB
    LAURSEN, T
    PALMER, GR
    HAYSOM, JE
    NOLAN, J
    TAPPING, RL
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 209 (01) : 52 - 61
  • [33] Twin hopping in nanolayered Zr-2.5Nb
    Zhang, Jie-Wen
    Leu, Brandon
    Kumar, M. Arul
    Beyerlein, Irene J.
    Han, Wei-Zhong
    [J]. MATERIALS RESEARCH LETTERS, 2020, 8 (08): : 307 - 313
  • [34] MODIFICATION OF THE STRUCTURE OF COLD-WORKED ZR-2.5 WT-PERCENT NB NUCLEAR-REACTOR PRESSURE TUBE MATERIAL
    NORTHWOOD, DO
    FONG, WL
    [J]. METALLOGRAPHY, 1980, 13 (02): : 97 - 115
  • [35] CREEP DUCTILITY OF COLD-WORKED ZR-2.5 WT-PERCENT NB AND ZIRCALOY-2 TUBES IN-REACTOR
    IBRAHIM, EF
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1981, 96 (03) : 297 - 304
  • [36] Characterization of different forms of Zr-2.5Nb samples before and after neutron irradiation
    Silva, Chinthaka
    Leonard, Keith
    Trammel, Michael
    Bryan, Chris
    [J]. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 716 : 296 - 307
  • [37] Effect of neutron irradiation on microstructure and mechanical properties of Zr-2.5Nb pressure tube
    Kim, YS
    Ahn, SB
    Oh, DJ
    Kim, SS
    Cheong, YM
    [J]. PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II, 2001, : 2775 - 2778
  • [38] Zr-silicide particles in Zr-2.5Nb pressure tube material: influence of oxidation and irradiation
    Lin, YP
    Perovic, V
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2000, 280 (01) : 120 - 125
  • [39] Effect of cold working and annealing on grain size and hardness of a Zr-2.5Nb alloy
    Kashyap, BP
    Pathak, R
    Kishore, R
    Fotedar, R
    Sinha, TK
    [J]. ZEITSCHRIFT FUR METALLKUNDE, 1998, 89 (04): : 303 - 310
  • [40] Effect of Cold Working and Annealing on Grain Size and Hardness of a Zr-2.5Nb Alloy
    Kashyap, Bhagwati Prasad
    Pathak, Rajeev
    Kishore, Ramaswamy
    Fotedar, Ramakrishna
    Sinha, Tapan Kumar
    [J]. International Journal of Materials Research, 1998, 89 (04): : 303 - 310