Delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tubes for PHWR700

S, Sunil Kumar; Bind, A.K.; Khandelwal, H. K.; Singh, R.N.; Chakravartty, J.K.

doi:10.1016/j.jnucmat.2015.08.002

Cited by 16 publications

(5 citation statements)

References 25 publications

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“…Current DHC experiments mainly focus on four points. The first is to describe the crack-propagation process by characterizing the fracture surface [ 136 ]. The second is to observe the precipitation and fracture behavior of hydrides on the cross-section during in situ DHC testing [ 137 ].…”

Section: Hydride-induced Embrittlementmentioning

confidence: 99%

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Jia

Han

2023

Materials

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Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research interests. For example, delayed hydride cracking induced a severe fracture and failure in a Zircaloy-2 pressure tube in 1983, causing the emergency shutdown of the Pickering nuclear reactor. Hydride has high hardness and very low toughness, and it tends to aggregate toward cooler or tensile regions, which initiates localized hydride precipitation and results in delayed hydride cracking. Notably, hydride reorientation under tensile stress substantially decreases the fracture toughness and increases the ductile-to-brittle transition temperature of Zr alloys, which reduces the safety of the long-term storage of spent nuclear fuel. Therefore, improving our knowledge of Zr hydrides is useful for effectively controlling hydride embrittlement in fuel assembly. The aim of this review is to reorganize the mechanisms of hydride nucleation and growth behaviors, hydride reorientation under external stress, and hydride-induced embrittlement. We revisit important examples of progress of research in this field and emphasize the key future aspects of research on Zr hydrides.

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Section: Hydride-induced Embrittlementmentioning

confidence: 99%

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Jia

Han

2023

Materials

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“…Although the computed stress fields give quantitative values of stresses in all direction and size of nodules, which are critical for DHC initiation qualitatively, it is not possible to determine size of the critical nodules quantitatively. In literature, reporting experimental results concerning DHC, a fatigue pre-crack is usually used [47,48]. Through the tests a threshold stress intensity factors have been determined [37,39,46,47].…”

Section: Stress Intensity Factors Calculationmentioning

confidence: 99%

“…In literature, reporting experimental results concerning DHC, a fatigue pre-crack is usually used [47,48]. Through the tests a threshold stress intensity factors have been determined [37,39,46,47].…”

Section: Stress Intensity Factors Calculationmentioning

confidence: 99%

“…Thus, stresses generated are increasing, which will indeed increase the values. The threshold stress intensity factor (K IH ) depends on the radial basal pole fraction in the matrix material and manufacturing routes [16,46,47], and typical values for unirradiated pressure tube material are reported to be between 8.5 and 10.5 MPa ffiffiffiffi ffi m p . To be on the conservative side, one may take the lower value K IH ¼ 8:5MPa ffiffiffiffi ffi m p for unirradiated materials, then nodules having aspect ratio less than 2 and a depth more than 350 mm may initiate crack growth DHC as shown in Fig.…”

Section: Stress Intensity Factors Calculationmentioning

confidence: 99%

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Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates

Murty

Singh

Ståhle

2019

Journal of Nuclear Materials

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In Fig. 1(a) and (b) plot of KJ as a function of aspect ratio of oxide nodules for different depths using unirradiated and irradiated material properties is shown. Also depicted in this figure are the reported values of threshold stress intensity factors above which crack growth by Delayed Hydride Cracking is possible. It is evident form figures that in cases of unirradiated material, oxide nodules having aspect ratios less than two and depths more than 350 mm can initiate DHC whereas nodules having aspect ratios less than 2.5 and depths more than 200 mm can initiate DHC in irradiated material.

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“…An increase in yield strength will result in a more brittle pipe failure [5]. It is very important as delay hydride cracking is one of the biggest issues for fuel channels and fuel claddings [6,7].…”

Section: Introductionmentioning

confidence: 99%

Numerical prediction of mechanical properties of zirconium alloy with hydrides using finite element method

Janulionis¹,

Dundulis²,

Kriūkienė³

et al. 2018

energetika

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During nuclear power plant (NPP) operation, degradation effects like ageing, corrosion, fatigue, and others may significantly impact component integrity. One of the degradation mechanisms is hydrogen absorption. High levels of hydrogen in zirconium alloys can lead to the formation of zirconium hydrides and that can influence material properties. Therefore, determination of material properties under different levels of hydrogen concentration in zirconium alloys is important. It is not always possible to conduct an experimental testing. Therefore, there is a need for alternative methods for determination of material properties. This article presents the numerical prediction of material properties of zirconium 2.5% niobium alloy with hydrides.According to the objective of the work, numerical prediction was performed using the finite element (FE) method. This was done by creating a finite element model of zirconium hydride embedded in zirconium alloy. The geometry and size of hydride were measured from a real specimen. The size of zirconium alloy surrounding the hydride was selected in such a way that hydride volume part in the model would match experimental measurements. The prognosis results were compared with the experimental data.

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Delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tubes for PHWR700

Cited by 16 publications

References 25 publications

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates

Numerical prediction of mechanical properties of zirconium alloy with hydrides using finite element method

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