Influence of metallurgical variables on delayed hydride cracking in Zr–Nb pressure tubes

Cirimello, Pablo; Domizzi, G.; Haddad, R.

doi:10.1016/j.jnucmat.2005.12.002

Cited by 34 publications

(6 citation statements)

References 17 publications

(35 reference statements)

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“…However, considering the large region from which hydrogen can flow to the crack tip, it was judged that the decrease in bulk hydrogen concentration would be small. This was also the assumption made recently in numerical evaluations of the model by Cirimello et al [12] and McRae et al [43].…”

Section: Theory Of Dhc Growth Ratesupporting

confidence: 68%

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Delayed Hydride Cracking: Theory and Experiment

Püls¹

2012

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

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As noted in Chaps. 1 and 9, zirconium alloy components can fail by a time-dependent mechanism of cracking if hydrides can preferentially form and subsequently crack at locations of elevated tensile stress. This process of time-dependent hydride cracking, called delayed hydride cracking (DHC), is based on the mechanism of diffusion of hydrogen to a region of elevated tensile stress followed by nucleation, growth, and fracture of the hydrided region. By repeating these steps, a crack can propagate in a component at a rate that, above a threshold stress intensity factor, K IH ; is mainly dependent on temperature. In this chapter we present the status of the present state of understanding of DHC in zirconium alloys, emphasizing the connections between the models developed and the experimental data. The intent of this chapter is not to provide an exhaustive review of the literature but to focus on results that are deemed to have collectively advanced our understanding of this phenomenon. This chapter is divided into two main parts, the first part dealing with DHC propagation, the other with DHC initiation. Although it may appear backwards to start with DHC propagation rather than initiation, this approach is consistent with the historical development of the field and thus also helps somewhat in simplifying the exposition. Readers wishing to obtain a succinct recent overview of DHC and other aspects of the effects of hydrogen and hydrides on the integrity of zirconium alloys are referred to a recent review by Coleman [15]. In addition, an earlier review by Northwood and Kosasih [47] provides a comprehensive summary account of work published in this field up to the date of that publication.M. P. Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components, Engineering Materials,

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Section: Theory Of Dhc Growth Ratesupporting

confidence: 68%

“…Later comparisons with other data also show good agreement [12,43]. The results obtained in the recent IAEA Coordinated Research Program on DHC growth rate measurements [16,26] summarizes the results obtained by different investigators participating in this research program.…”

Section: Dependence On Yield Strengthmentioning

confidence: 62%

Delayed Hydride Cracking: Theory and Experiment

Püls¹

2012

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

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“…The improved material properties of these alloys are attributed to microstructural features associated with the presence of Nb. A precipitation of β − Nb phase having body centered cubic structure in α − Zr matrix of hexagonal closed packed structure results in corrosion and hydrogenation resistance [1][2][3][4][5]. It was shown that Nb addition to the zirconium alloys can play an important role in terms of the terminal solid solubility for increasing the life-time of cladding [6].…”

Section: Introductionmentioning

confidence: 99%

Phase field modeling of precipitation in Zr-1%Nb-1%Sn alloy: A study of statistical properties and mechanical response

Kharchenko

Kong²,

Xin³

et al. 2023

Phys. Scr.

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We develop the phase field model to simulate precipitation of secondary phase in ternary alloys with extra-small content of doping. This approach is applied to study $\beta$-phase precipitation in the model system of commercial alloy Zr-Nb-Sn at thermal treatment. An analysis of local rearrangement of doping and equilibrium vacancies during precipitation has shown that the dissolved Tin is mostly segregated around phase interface by trapping vacancies. Kinetics of precipitation, size and distribution of the precipitates, concentration of the species in precipitates and matrix are studied where it is revealed that Lifshits-Slyozov-Wagner distribution can be used to predicate statistical properties of precipitates. Mechanical response including the plastic deformations in precipitated solid is discussed. It is shown that yield strength change increases during precipitation. Yield and ultimate stresses are studied at different shear rates for the annealed alloy. A transition to plastic flow is described by means of dislocation structure evolution. Formation and growth of slip planes and dislocation loop-precipitate interaction governed by elastic moduli difference is analyzed. It is shown that emergence of dislocation loops around precipitates follows the Orowan mechanism.

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“…For example, Zircalloy high-pressure-tubes used in light water reactors are known to absorb deuterium which can cause delayed hydride cracking (Cirimello, G. et al 2006). Similarly, in Pebble Bed Modular reactors and in other technologies based on inert gas cooling, formation of ionic gas bubbles within both fuel and structural materials is common (Was 2007).…”

Section: Introductionmentioning

confidence: 99%

Multiscale Materials Modeling of Structural Materials for Next Generation Nuclear Reactors

Deo¹

2012

Nuclear Reactors

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Influence of metallurgical variables on delayed hydride cracking in Zr–Nb pressure tubes

Cited by 34 publications

References 17 publications

Delayed Hydride Cracking: Theory and Experiment

Delayed Hydride Cracking: Theory and Experiment

Phase field modeling of precipitation in Zr-1%Nb-1%Sn alloy: A study of statistical properties and mechanical response

Multiscale Materials Modeling of Structural Materials for Next Generation Nuclear Reactors

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