Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors

Abolhassani, S.; Bart, G.; Bertsch, Johannes; Große, M.; Hallstadius, Lars; Hermann, Armin; Kuri, G.; Ledergerber, G.; Lemaignan, C.; Martin, Matthias; Portier, S.; Proff, Christian; Restani, Renato; Valance, Stéphane; Valizadeh, Sima; Wiese, Holger

doi:10.1520/stp154320130007

Cited by 12 publications

(8 citation statements)

References 18 publications

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“…It should be kept in mind that this material is not designed to stay for such long residence times in reactor, and the 9-cycle cladding was produced for research activities only. The hydrogen pickup fraction of the cladding after 9 cycles had reached 30% compared to the 3-cycle cladding which was 17% [6]. This finding forms the basis for the motivation for the extensive characterisation and comparison of its high and low burnup samples [6], [19]- [23].…”

Section: Introductionmentioning

confidence: 78%

“…Hydrogen uptake and subsequent hydride formation during component lifetime has been identified as one of the critical life limiting degradation behaviours for these components [2]- [5]. It has been demonstrated by recent studies that hydrogen uptake is not constant throughout component lifetime and it can increase or decrease with residence time [4], [6]. To explain the mechanism of hydrogen uptake and its variation from one alloy to another, (or for the same alloy at different stages of oxidation and irradiation), the oxide electronic resistivity is considered.…”

Section: Introductionmentioning

confidence: 99%

“…Using micromanipulators (micromanipulator) in a scanning electron microscope (SEM), the resistivity of a certain thickness of oxide at a certain point could be directly measured. Although this paper will cover to some extent the experimental method, further detail for the hydrogen measurements and for the conductivity technique can be found in refs [6] and [17], [18]. The results will then be compared with the hydrogen uptake for both materials, previously measured in ref.…”

Section: Introductionmentioning

confidence: 99%

“…The results will then be compared with the hydrogen uptake for both materials, previously measured in ref. [6].…”

Section: Introductionmentioning

confidence: 99%

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Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups

Hawes

Baris

Chiu

et al. 2020

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 78%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

“…The results will then be compared with the hydrogen uptake for both materials, previously measured in ref. [6].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups

Hawes

Baris

Chiu

et al. 2020

Journal of Nuclear Materials

Self Cite

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“…The in‐depth SIMS data can be used to generate 1‐dimensional (1D) depth profiles of the kind more commonly reported for HPU studies 7,41,13 . Typical depth profiles for 1 H – and 2 H – signals through the oxide into the metal matrix are shown in Figure 5.…”

Section: Resultsmentioning

confidence: 99%

Site‐specific specimen preparation for SIMS analysis of radioactive samples

Liu

Lozano-Pérez

et al. 2020

Journal of Microscopy

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Secondary Ion Mass Spectrometry is an important technique for the study of the composition of a wide range of materials because of the exceptionally high sensitivity that allows the study of trace elements and the ability to distinguish isotopes that can be used as markers for reactions and transport processes. However, when studying nuclear materials, it is often necessary to analyse highly radioactive samples, and only rather few SIMS facilities are available in active environments. In this paper, we present a methodology using focussed ion beam milling to prepare samples from radioactive specimens that are sufficiently large to undertake SIMS mapping experiments over microstructurally significant regions, but with overall activities small enough to be readily transported and analysed by a SIMS instrument in a normal laboratory environment. Radioactive samples prepared using this methodology can also be used for correlative SIMS analysis with other analytical microscopies. SIMS results showing the distributions of deuterium in oxides on in‐reactor corroded zirconium alloys are presented to demonstrate the potential of this sample preparation technique.

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Fracture behaviour of Zr(Fe,Cr)2 Laves phase precipitates in Zircaloy-4 subjected to β forging

Ali

Han

Ren

et al. 2023

Journal of Alloys and Compounds

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Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors

Cited by 12 publications

References 18 publications

Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups

Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups

Site‐specific specimen preparation for SIMS analysis of radioactive samples

Fracture behaviour of Zr(Fe,Cr)2 Laves phase precipitates in Zircaloy-4 subjected to β forging

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