Effect of Irradiation on Terminal Solid Solubility of Hydrogen in Zr-2.5Nb

被引:5
|
作者
Nordin, Heidi M. [1 ]
Hilton, Vicky [1 ]
Buyers, Andrew W. [1 ]
Coleman, Christopher E. [1 ]
McRae, Glenn A. [2 ]
机构
[1] Canadian Nucl Labs, Chalk River Labs, 286 Plant Rd, Chalk River, ON K0J 1J0, Canada
[2] Carleton Univ, Dept Mech & Aerosp Engn, 1125 Colonel By Dr, Ottawa, ON K1S 5B6, Canada
关键词
Zr-2.5Nb; terminal solid solubility (TSS); hydrogen solubility limit; irradiation; differential scanning calorimetry (DSC); ALPHA-PHASE; ZIRCONIUM; LIMITS; ALLOY; ZIRCALOY-2; DEUTERIUM;
D O I
10.1520/STP159720160044
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Knowledge of the temperature dependence of hydrogen solubility is used to define the conditions necessary for brittle hydrides to be present in reactor components during service. The terminal solid solubility (TSS) of hydrogen is affected by several factors, including irradiation, cold work, and decomposition of the beta phase in Zr-2.5Nb. TSS temperatures for specimens irradiated in Osiris, Halden, and CANDU (R) reactors are reported. TSS was measured on Zr-2.5Nb specimens using differential scanning calorimetry (DSC) to complete four heat-up/cool-down cycles (heat to a peak temperature and cool to room temperature at a rate of 10 degrees C/min) followed by a 1-h anneal at 500 degrees C, and then four more heat-up/cool-down cycles. As with Zircaloy, irradiation slightly decreases the TSS temperatures, but subsequent annealing increases them. These changes are attributed to an initial effect of irradiation damage and reconstitution of the beta phase and reversal of these effects by annealing, as indicated by X-ray diffraction data showing reduced dislocation density and higher beta-phase volume fraction after the specimens were annealed.
引用
收藏
页码:1136 / 1166
页数:31
相关论文
共 50 条
  • [41] 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
  • [42] 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
  • [43] Irradiation-enhanced deformation of Zr-2.5Nb tubes at high neutron fluences
    Causey, AR
    Holt, RA
    Christodoulou, N
    Ho, ETC
    [J]. ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 : 74 - 85
  • [44] The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing
    Walters, L.
    Bickel, G. A.
    Griffiths, M.
    [J]. ZIRCONIUM IN THE NUCLEAR INDUSTRY, 2015, 1543 : 693 - 725
  • [45] Modelling of the Zr-2.5Nb alloy properties with hydrides
    Dundulis, G.
    Karalevcius, R.
    Janulionis, R.
    Grybenas, A.
    [J]. MECHANIKA, 2007, (02): : 23 - 26
  • [46] Influence of hydrogen content on impact toughness of Zr-2.5Nb pressure tube alloy
    Singh, R. N.
    Viswanathan, U. K.
    Kumar, Sunil
    Satheesh, P. M.
    Anantharaman, S.
    Chakravartty, J. K.
    Stahle, P.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (07) : 2425 - 2436
  • [47] Mechanism of deuterium pickup in Zr-2.5Nb alloy
    Ploc, RA
    [J]. MATERIALS AT HIGH TEMPERATURES, 2000, 17 (01) : 29 - 34
  • [48] Investigation of J-integral for hydrogen saturated Zr-2.5Nb zirconium alloy
    Daunys, M.
    Dundulis, R.
    Krasauskas, P.
    [J]. MECHANIKA 2007, PROCEEDINGS, 2007, : 62 - 67
  • [49] Microsegregation of oxygen in Zr-2.5Nb alloy materials
    Choubey, R
    Jackman, JA
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1996, 27 (02): : 431 - 440
  • [50] Kinetics of the δ to γ zirconium hydride transformation in Zr-2.5Nb
    Root, JH
    Small, WM
    Khatamian, D
    Woo, OT
    [J]. ACTA MATERIALIA, 2003, 51 (07) : 2041 - 2053