首页|Diffusion of H in Zircaloy-2 and Zr-2.5%Nb rolled plates between 250 degrees C and 350 degrees C by off-situ neutron imaging experiments

Diffusion of H in Zircaloy-2 and Zr-2.5%Nb rolled plates between 250 degrees C and 350 degrees C by off-situ neutron imaging experiments

扫码查看
Zirconium alloys in nuclear power plants operate in high-pressure water at temperatures between 250 and 350 degrees C. Hydrogen (or deuterium) ingress due to waterside corrosion and if the solubility is exceeded H precipitates as a brittle hydride phase. Degradation mechanisms involve the accumulation of these brittle hydrides at cold spots or crack tips, as a result of H redistribution in response to thermal and stress gradients, respectively. Knowledge of H diffusion coefficients at operating temperatures is central to evaluating the rate of hydride accumulation and crack growth velocity. We determine the diffusion coefficients of H in Zircaloy-2 and Zr-2.5%Nb rolled plates at 250 degrees C, 300 degrees C and 350 degrees C along the rolling and normal directions by neutron imaging experiments with sensitivity of 5 wt ppm H for a spatial resolution 0.04 mm x 2 mm. These values were evaluated from H concentration profiles measured at room temperature on specimens of dimensions 10 x 10 x 4 mm(3) containing a hydride layer on one face, after annealing treatments between 60 and 600 min. This allowed the identification of a transition zone of 200-300 mu m between the hydride layer and the Zr alloy material, composed by large, sparsely distributed hydrides. In Zircaloy-2 plates, no substantial differences were observed in H diffusion along different directions or metallurgical conditions, and diffusion coefficients (0.6 +/- 0.1 10(-10) m(2)/s at 300 degrees C). By contrast, in hot rolled Zr-2.5%Nb plates the diffusion along the rolling direction (5.5 +/- 0.5 x 10(-10) m(2)/s at 300 degrees C) was much faster than along the normal direction (2.5 +/- 0.7 10(-10) m(2)/s at 300 degrees C), very likely due to H diffusing along the continuous network of beta filaments. After a thermal treatment of 3 h at 860 degrees C the plate microstructure changed generating radically changed H diffusion coefficients, resulting in H diffusion being much faster along the normal direction (4.0 +/- 0.5 10(-10) m(2)/s at 300 degrees C) than along the rolling direction (1.4 +/- 0.5 10(-10) m(2)/s at 300 degrees C). (c) 2022 Elsevier B.V. All rights reserved.

Hydrogen embrittlementSolid diffusionZirconium alloysNeutron imagingZIRCONIUM ALLOYSHYDROGEN DIFFUSIONALPHA-PHASEZR-2.5NBTRANSFORMATIONCOEFFICIENTSDEUTERIUMBEHAVIORSTRESSZR

Luzin, V.、Hache, M.、Barrow, L.、Daymond, M. R.、Santisteban, J. R.、Buitrago, N. L.、Riffo, A. Moya、Soria, S. R.、Baruj, A. L.、Schulz, M.、Grosse, M.

展开 >

ANSTO

Queens Univ

Comis Nacl Energia Atom

CONICET Consejo Nacl Invest Cient & Tecn

Tech Univ Munich

Karlsruher Inst Technol

展开 >

2022

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN:0022-3115
年,卷(期):2022.561
  • 6
  • 35