In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes

Holt, R.A.

doi:10.1016/j.jnucmat.2007.02.017

Cited by 204 publications

(108 citation statements)

References 56 publications

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“…The <a>-type loop lies on a prism plane with a Burgers vector ð1=3ð1120ÞÞ in the <a> direction of the hcp lattice and is the most readily observable change. The <a>-type loops are very small, only a few tens of nanometres in the α grains, and shown as "black spots" [12]. The <a>-type dislocation loops are the most common ones in zirconium alloys produced by irradiation.…”

Section: Dislocation Loopsmentioning

confidence: 99%

“…The dislocation densities increase rapidly at low neutron fluence (<1 × 10 25 n·m −2 , roughly 1 year of operation), and then achieves a steady state [16,17] (Figure 3). The saturation level is a function of temperature and fast flux, increasing with fast flux and decreasing with temperature [12].…”

Section: Dislocation Loopsmentioning

confidence: 99%

“…As shown in Figure 3, the c-component dislocation structure is evolving gradually with increasing high fluencies. Unlike the <a>-type loop, it is strictly a vacancy-type loop [19], and it is relatively larger (100 nm) than the <a>-type loops, with a much lower density [12].…”

Section: Dislocation Loopsmentioning

confidence: 99%

“…At normal reactor operating condition, thermal creep does not contribute significantly to component deformation. The most common practice is to assume that each component is independent of the other 2, and the total deformation is the sum of the 3 components [12].…”

Section: Irradiation Effect On Dimensional Change (Creep Andmentioning

confidence: 99%

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Irradiation Effects on ZR-2.5NB in Power Reactors

Song

2016

CNL Nuclear Review

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Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, “High Power Channel-type Reactor”) reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr-2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge.

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Section: Dislocation Loopsmentioning

confidence: 99%

Section: Dislocation Loopsmentioning

confidence: 99%

Section: Dislocation Loopsmentioning

confidence: 99%

Section: Irradiation Effect On Dimensional Change (Creep Andmentioning

confidence: 99%

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Irradiation Effects on ZR-2.5NB in Power Reactors

Song

2016

CNL Nuclear Review

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“…with the equilibrium volume fraction of b-phase of about 10% is used, among other things, as the pressure tube material for CANada Deuterium Uranium (CANDU) reactors [2]. It is, thus, important to understand the fundamentals of deformation mechanisms in these alloys.…”

mentioning

confidence: 99%

Load partitioning and evidence of deformation twinning in dual-phase fine-grained Zr–2.5%Nb alloy

Muránsky¹,

Daymond²,

Bhattacharyya³

et al. 2013

Materials Science and Engineering: A

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is an open access repository that collects the work of Arts et Métiers ParisTech researchers and makes it freely available over the web where possible. a b s t r a c tIn situ neutron diffraction loading experiments were carried out on a cold-rolled dual-phase (a-phase, $ 10% b-phase) Zr-2.5%Nb alloy at room temperature. The specimens were cut at different angles from the rolling direction (RD) towards the transverse direction (TD), thus the loading axis changes gradually from the rolling to transverse direction. Due to the strong texture of the studied alloy, and unidirectional nature of deformation twinning, the changing loading direction with respect to initial texture has a significant impact on the collaborative slip-twinning deformation mode in the hexagonal close-packed (hcp) a-phase. The present neutron diffraction results provide direct evidence of {1 À 1.2}/1 À 1. À 1S ''tensile'' twins in the a-phase of dual-phase Zr-2.5%Nb alloy at room temperature.Additionally, TEM analysis was employed to confirm the presence of ''tensile'' twins, and determine if other type of twins were present. It is further clear from the neutron diffraction results that applied load is gradually transferred from the plastically softer a-phase to the plastically harder b-phase which acts as a reinforcing phase having a yield strength in the range 750-900 MPa depending on the loading direction.

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