Oxide microstructure and deuterium ingress in Zr-2.5Nb CANDU® pressure tubes

被引:5
|
作者
Woo, OT [1 ]
Lin, YP
Khatamian, D
机构
[1] Atom Energy Canada Ltd, Chalk River Labs, Chalk River, ON K0J 1J0, Canada
[2] Kinectrics, Toronto, ON M8Z 6C4, Canada
关键词
irradiated oxide microstructure; deuterium ingress; Zr-2.5; Nb;
D O I
10.3184/096034003782750178
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The microstructures of oxides grown on the inside surface (water-side) of Zr-2.5Nb pressure tubes removed from CANDU(R)* reactors were characterised by TEM and correlated with deuterium ingress. Oxide cross-sections consisted of two structurally distinct regions: a columnar oxide region next to the metal/oxide interface, and an outer coarse equiaxed oxide region. Near the metal/oxide interface, the microstructure consisted of columnar grains without overt porosity. Away from the interface, the oxide consisted of coarsened equiaxed grains with (100)(m)-twins, grain-boundary cracks and nanopores. The oxide microstructures on various pressure tubes differ in the proportion of equiaxed grains. Electron micrographs suggest that a larger proportion of equiaxed grains is associated with higher deuterium uptake. The predominance of grain-boundary cracks in equiaxed oxides indicates that they are likely more permeable to water than columnar oxides. Energy dispersive X-ray analyses revealed substantial amounts of Fe-K-alpha (and Mn-K-alpha) in the equiaxed oxide grains at the outermost surface. Energy Dispersive X-ray mapping of Fe-K-alpha and detection of the Mn-K-alpha (produced by neutron activation of Fe-54 and subsequent decay of Fe-55) in the absence of external excitation, unequivocally demonstrated that the iron had accumulated in the oxide during reactor operation. The Fe concentration was highest near the outermost region, and decreased inwards towards the metal/oxide interface. These results are consistent with permeable equiaxed oxides picking up considerable amounts of Fe at the outermost region from the heavy water coolant.
引用
收藏
页码:593 / 600
页数:8
相关论文
共 50 条
  • [41] ROLE OF MICROSEGREGATION IN FRACTURE OF COLD-WORKED ZR-2.5NB PRESSURE TUBES
    AITCHISON, I
    DAVIES, PH
    JOURNAL OF NUCLEAR MATERIALS, 1993, 203 (03) : 206 - 220
  • [42] Micro-texture of extruded Zr-2.5Nb tubes
    Holt, RA
    Zhao, PS
    JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (03) : 520 - 528
  • [43] Development and Characterization of Microstructure and Mechanical Properties of Heat-Treated Zr-2.5Nb Alloy for AHWR Pressure Tubes
    Singh, R. N.
    Bind, A. K.
    Singh, J. B.
    Chakravartty, J. K.
    Paul, V. Thomas
    Madhusoodnan, K.
    Suwas, Satyam
    Saroja, S.
    Suri, A. K.
    Banerjee, S.
    MATERIALS PERFORMANCE AND CHARACTERIZATION, 2013, 2 (01) : 120 - 133
  • [44] Separation of Zr from Zr-2.5Nb by Electrorefining in LiCl-KCl for Volumetric Decontamination of CANDU Pressure Tube
    Hur, Jungho
    Jeong, Seongjin
    Sohn, Sungjune
    Park, Jaeyeong
    Hwang, Il Soon
    APPLIED SCIENCES-BASEL, 2021, 11 (09):
  • [45] Study of microstructure, texture and mechanical properties of Zr-2.5Nb alloy pressure tubes fabricated with different processing routes
    Saibaba, N.
    Vaibhaw, Kumar
    Neogy, S.
    Krishna, K. V. Mani
    Jha, S. K.
    Babu, C. Phani
    Rao, S. V. Ramana
    Srivastava, D.
    Dey, G. K.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 440 (1-3) : 319 - 331
  • [46] Stress assisted oxide cracking of Zr-2.5Nb pressure tube material
    Gopalan, Avinash
    Sunil, Saurav
    Murty, T. N.
    Bind, A. K.
    Kumawat, B. K.
    Chandanshive, S. A.
    Singh, R. N.
    JOURNAL OF NUCLEAR MATERIALS, 2020, 536 (536)
  • [47] EFFECT OF HEAT TREATMENT ON MICROSTRUCTURE CHARACTERISTICS OF HOT WORKED ZR-2.5NB ALLOY TUBES
    Yin, Jianming
    Gao, Bo
    Luan, Baifeng
    Zhang, Yan
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, ICONE31 2024, 2024,
  • [48] Microtexture analysis of Zr-2.5Nb pressure tubing
    Griffiths, M
    Holt, RA
    Li, J
    Saimoto, S
    ANALYSIS OF IN-SERVICE FAILURES AND ADVANCES IN MICROSTRUCTURAL CHARACTERIZATION, 1999, 26 : 293 - 302
  • [49] 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
    PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II, 2001, : 2775 - 2778
  • [50] Residual carbon impurities in Zr-2.5Nb and their effect on deuterium pickup
    Ploc, RA
    JOURNAL OF NUCLEAR MATERIALS, 2000, 279 (2-3) : 344 - 350