首页|Hydrogen trapping by irradiation-induced defects in 316 Lstainless steel: A combined experimental and modeling study

Hydrogen trapping by irradiation-induced defects in 316 Lstainless steel: A combined experimental and modeling study

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  • NSTL
  • Elsevier
The irradiation-induced defects in stainless steel internal components of pressurized water reactors combined with hydrogen uptake during the oxidation process could be a key parameter in the mechanism for Irradiation-Assisted Stress Corrosion Cracking (IASCC). A heat-treated 316 L SS containing a low amount of defects was Fe3+ ions-implanted; irradiation-induced defects types and depth distributions were characterized by Transmission electron microscopy (TEM). Deuterium was then inserted in the specimens either by cathodic charging or by sample exposure to deuterated primary water. Secondary Ions Mass Spectrometry - SIMS - permitted to access the deuterium distribution at the implanted stainless steel surface. A finite difference numerical solver accounting for hydrogen diffusion/trapping coupling was used to simulate the hydrogen transport in the implanted material, taken into consideration the specific heterogeneous character of the irradiation-induced defects distribution in matter. Taking as input data the experimental defects distribution associated with Frank loops or voids, the main trapping sites for hydrogen were assigned to voids, not Frank loops. Such numerical approach was able to deal accurately with the problem of hydrogen transport in a heterogeneous material as well as to differentiate two potential trap sites contributions to the experimental deuterium distribution. In addition, according to results obtained after primary water exposure, trapping at voids was still effective at 320 degrees C, signature of a high binding energy of hydrogen in voids. (C) 2022 Elsevier B.V. All rights reserved.

Hydrogen trappingIrradiation defectsAustenitic stainless steelSecondary ions mass spectrometryModelingSTRESS-CORROSION CRACKINGSTAINLESS-STEELMICROSTRUCTURE EVOLUTIONOXIDE-FILMTHERMAL-DESORPTIONASSISTED CRACKINGPRIMARY WATERBEHAVIORMECHANISMDIFFUSION

Bach, Anne-Cecile、Martin, Frantz、Duhamel, Cecilie、Perrin, Stephane、Jomard, Francois、Crepin, Jerome

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Univ Paris Saclay

PSL Univ

Univ Montpellier

UVSQ

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2022

10.1016/j.jnucmat.2022.153603

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.562
  • 3
  • 59