Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding

Colldeweih, Aaron W.; Bertsch, Johannes

doi:10.1016/j.jnucmat.2022.153737

Cited by 11 publications

(5 citation statements)

References 27 publications

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“…The samples were first fatigue pre-cracked at room temperature according to previously reported procedures [15,32]. Subsequent to the propagation of the sharp initiation crack, the samples were mechanically unloaded and heated above the respective temperature of terminal solid solubility of hydrogen for dissolution (TSSD) and held for 1 h prior to cooling at 30 • C/h until reaching the test temperature [15,[32][33][34]. Following the stabilization of the test temperature, the starting mechanical load l o was applied.…”

Section: Dhc Testing and Slow-cooling Proceduresmentioning

confidence: 99%

“…As the K I value is near constant, and well below the fracture toughness of the hydrogen free material [35], subcritical cracking conditions are provided for DHC to occur. Further details on the loading scheme and test parameters can be found in the following reference in where the identical test set up is employed [32].…”

Section: Dhc Testing and Slow-cooling Proceduresmentioning

confidence: 99%

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Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

et al. 2023

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Section: Dhc Testing and Slow-cooling Proceduresmentioning

confidence: 99%

Section: Dhc Testing and Slow-cooling Proceduresmentioning

confidence: 99%

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

et al. 2023

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“…Hydrogen has also been found to enhance intermetallic diffusion [109]. Enhanced irradiation defect growth has also been attributed to the presence of hydrogen [110][111][112].…”

Section: Hydrogen In Fission Moderators Cladding and Structural Mater...mentioning

confidence: 99%

Helium and Hydrogen Effects in Structural Materials for Nuclear Applications

Karpov¹,

Tolstolutskaya²

2022

Problems of Atomic Science and Technology

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Displacement cascades produce a variety of defects under reactor conditions, but of particular concern is the simultaneous production of helium (He) and hydrogen (H), which enhances the degradation of structural materials. The overall majority of performed studies on helium and hydrogen interactions with materials were based on ion beam irradiation, which served as a convenient tool for the simulation of neutrons exposure over a variety of temperature and dose regimes due to the ability to widely vary and control the irradiation parameters. Experimental investigations of the hydrogen-defect interaction performed by thermal desorption spectroscopy, and the parameters of this interaction obtained by numerical simulations based on diffusion-trapping codes are debated. In this review, we also summarize previous studies on grain boundaries and nanoprecipitate effects on hydrogen transport in metals, as well as the role of hydrogen in the corrosion and cracking of steels. We discuss here issues of helium bubbles formation and some of the evidence for the synergistic effects of hydrogen and helium in the presence of displacement damage, and their influence on irradiation hardening and swelling. Particular attention was devoted to the features of hydrogen interaction with noble-gas bubbles, which were considered on the basis of most recent published data.

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“…A constant tensile load was used in Kubo et al (2012) using constant or decreasing temperature. Colldeweih and Bertsch (2022) used a compressed precracked arc-shaped specimen at constant temperature and the load was decreased until crack arrest. In all cases, the crack was inserted on the outer surface of the specimens.…”

Section: Introductionmentioning

confidence: 99%

Assessing the fracture toughness of Zircaloy-4 fuel rod cladding tubes: impact of delayed hydride cracking

François,

Petit,

Auzoux

et al. 2024

Int J Fract

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Delayed Hydride Cracking (DHC) is a hydrogen embrittlement phenomenon that may potentially occur in Zircaloy-4 fuel claddings during dry storage conditions. An experimental procedure has been developed to measure the toughness of this material in the presence of DHC by allowing crack propagation through the thickness of a fuel cladding. Notched C-ring specimens, charged with 100 wppm of hydrogen, were used and pre-cracked by brittle fracture of a hydrided zone at the notch root at room temperature. The length of the pre-crack was measured on the fracture surface or cross-sections. Additionally, a finite element model was developed to determine the stress intensity factor as a function of the crack length for a given loading. Two types of tests were conducted independently to determine the fracture toughness with and without DHC, K I DHC and K I C , respectively: (i) constant load tests at 150°C, 200°C, and 250°C; (ii) monotonic tests at 25°C, 200°C, and 250°C. The results indicate the following: (1) there is no temperature influence on the DHC toughness of Zircaloy-4 between 150 and 250°C (K I DHC ∈ [7.2; 9.2] MPa √ m), (2) within this temperature range, the fracture toughness of Zircaloy-4 is halved by DHC (K I C ∈ [16.9; 19.7] MPa √ m), (3) the crack propagation rate decreases with decreasing temperature and (4) the time before crack propagation increases as the temperature and loading decrease.

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Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding

Cited by 11 publications

References 27 publications

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

Helium and Hydrogen Effects in Structural Materials for Nuclear Applications

Assessing the fracture toughness of Zircaloy-4 fuel rod cladding tubes: impact of delayed hydride cracking

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