Mechanisms of hydrogen induced delayed cracking in hydride forming materials

Dutton, R.; Nuttall, K.; Püls, M. P.; Simpson, L. A.

doi:10.1007/bf02644858

Cited by 226 publications

(111 citation statements)

References 34 publications

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“…Therefore the present numerical simulation is in agreement with the development of striations during delayed hydride cracking (e.g. [2], [3]). According to Fig.…”

Section: Hydride Precipitation and Fracture Under K-field Dominancesupporting

confidence: 76%

“…At t = 4 days, hydride volume fraction, f, is greater or equal to 0.90 within the range of 2.5 µm ≤ x 1 ≤12.4 µm. The development of the area ahead of the crack tip, which is rich in hydride volume fraction, can be interpreted as the precipitation of near-tip hydrides of size about equal to 10 µm, in agreement with the interstriation spacing and the hydride platelet size, observed in delayed hydride cracking experiments [2], [7], [3]. At t = 4.36 days, the hydride volume fraction is relatively small ahead of the crack tip over a distance of the order of 10 µm.…”

Section: Hydride Precipitation and Fracture Under K-field Dominancesupporting

confidence: 58%

“…Then, delayed hydride cracking, a subcritical crack growth mechanism, may occur, e.g. [2]- [4], [7], [11].…”

Section: Introductionmentioning

confidence: 99%

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Hydride-Induced Embrittlement in Metals — Stress and Temperature Effects

Varias

Massih

2003

IUTAM Symposium on Field Analyses for Determination of Material Parameters — Experimental and Numerical Aspects

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A robust mathematical model for the hydrogen embrittlement of hydride forming metals has been developed. The model takes into account the coupling of the operating physical processes, namely: (i) hydrogen diffusion, (ii) hydride precipitation, (iii) non-mechanical energy flow, and (iv) hydride/solid-solution deformation. Crack growth is simulated by using a new version of de-cohesion model with time-dependent energy of de-cohesion due to the gradual process of hydride formation. Zircaloy-2 hydrogen embrittlement and fracture initiation have been studied by using a finite element implementation of the model. Delayed hydride cracking has been considered in two configurations: (i) a semi-infinite crack, under mode-I K-field dominance and constant temperature, and (ii) a cracked plate, under tensile stress and temperature gradient. The initial and boundary conditions, in case (ii), are those encountered in the fuel cladding of boiling water reactors, during operation, and lead to loss of K-field dominance soon after the application of loading. The numerical simulation predicts hydride precipitation at some distance from the crack tip. The near-tip hydride platelets fracture, when the remote loading is sufficiently strong, and leave behind ligaments, which are stretched plastically, in agreement with experimental observations. The numerical results on hydride size, incubation period and crack growth velocity are compared with experimental data.Further development of the model should be combined with accurate experimental determination of the mechanical and thermal properties of the hydrides.

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“…Therefore the present numerical simulation is in agreement with the development of striations during delayed hydride cracking (e.g. [2], [3]). According to Fig.…”

Section: Hydride Precipitation and Fracture Under K-field Dominancesupporting

confidence: 76%

Section: Hydride Precipitation and Fracture Under K-field Dominancesupporting

confidence: 58%

See 1 more Smart Citation

Hydride-Induced Embrittlement in Metals — Stress and Temperature Effects

Varias

Massih

2003

IUTAM Symposium on Field Analyses for Determination of Material Parameters — Experimental and Numerical Aspects

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“…사용후핵연료의 건전성에 영향을 미칠 수 있는 요인 들로는 크립(creep) [5][6][7]과 수소화물재배열 [8][9][10], 지연수 소화균열(Delayed Hydride Cracking, DHC) [11][12][13], 응력 부식균열 [14,15], 산화 및 부식에 의한 파괴 등을 들 수 있 다 [16]. 미국 원자력안전규제위원회(U.S. Nuclear Regula- …”

Section: 서 론unclassified

Review on Spent Nuclear Fuel Performance and Degradation Mechanisms under Long-term Dry Storage

Kim¹,

Kook²,

Sim³

et al. 2013

Journal of the Nuclear Fuel Cycle and Waste Technology

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As the capacity of spent nuclear fuel storage pool at reactor sites becomes saturated in ten years, long term dry storage strategy has been recently discussed as an alternative option in Korea. In this study, we reviewed safetycriteria-related research results on spent nuclear fuel performance and integrity under long-term dry storage and proposed the direction and the scope of future domestic research and development. Creep and hydride effect in relation to the embrittlement are known to be the major degradation mechanisms of the spent fuels during the long term dry storage. However, recent research results showed that hydride reorientation and hydride embrittlement are one of the most critical factors to the spent fuel integrity. Accordingly safety criteria of US and Japan for the storage system are basically founded on those mechanisms. However, in Korea, not only in-pile but out-of-pile experimental data have not been generated to understand fuel cladding degradation and to determine the criteria to ensure the safety. In addition, the transient behavior of the spent fuel during transportation also needs to be thoroughly examined. Therefore, various experimental research and development will be required to establish our own safety criteria for future long-term dry storage of domestic spent fuels.

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“…Delayed failure due to hydriding has been However, a Zircaloy-2 pressure tube did fail recently (August Although reported in local newspapers in A series of papers deals with delayed hydride cracking (Puls et al, 1982;Hillner, 1982;Dutton, 1978;Dutton et al, 1977;Simpson and Puls, 1979;Simpson and Cann, 1979). which in turn requires hiqh stress intensity factors.…”

Section: Simpson Ibid)mentioning

confidence: 99%

Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

Rothman¹

1984

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Mechanisms of hydrogen induced delayed cracking in hydride forming materials

Cited by 226 publications

References 34 publications

Hydride-Induced Embrittlement in Metals — Stress and Temperature Effects

Hydride-Induced Embrittlement in Metals — Stress and Temperature Effects

Review on Spent Nuclear Fuel Performance and Degradation Mechanisms under Long-term Dry Storage

Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

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