Zirconium in the Nuclear Industry: Eleventh International Symposium 1996
DOI: 10.1520/stp16177s
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Oxide Characteristics and Corrosion and Hydrogen Uptake in Zr-2.5 Nb CANDU Pressure Tubes

Abstract: Oxides on removed pressure tubes from Pickering Unit 3 after 13.4 effective full power years (EFPY) have been examined to investigate the cause of variability in bulk alloy deuterium contents in outlet regions in order to improve predictions and minimize deuterium uptake in operating CANDU reactors. Secondary ion mass spectroscopy (SIMS) and electrochemical impedance spectrometry (EIS) were used for characterization with minimal sample preparation and modification. Two SIMS techniques were used for quantificat… Show more

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Cited by 9 publications
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“…Since Ni accelerates hydrogen absorption corrosion, Ni was later removed, the Fe content was increased to strengthen corrosion resistance, and a Zircaloy-4 (Zr-4) alloy was developed [19], which is basically equivalent to the Zr-2 alloy's mechanical properties and corrosion resistance under the same heat treatment conditions. Due to the small thermal neutron absorption section and the effect of strengthening the alloy of the Nb element, Zr-Nb series alloys, such as E110 [20], M5 [21], and Zr-2.5 Nb [22], were developed. As mentioned previously, the properties of the irradiation defect formation, corrosion behaviors, and irradiationinduced embrittlement and hardening in normal operational conditions are of paramount concern.…”
Section: Introductionmentioning
confidence: 99%
“…Since Ni accelerates hydrogen absorption corrosion, Ni was later removed, the Fe content was increased to strengthen corrosion resistance, and a Zircaloy-4 (Zr-4) alloy was developed [19], which is basically equivalent to the Zr-2 alloy's mechanical properties and corrosion resistance under the same heat treatment conditions. Due to the small thermal neutron absorption section and the effect of strengthening the alloy of the Nb element, Zr-Nb series alloys, such as E110 [20], M5 [21], and Zr-2.5 Nb [22], were developed. As mentioned previously, the properties of the irradiation defect formation, corrosion behaviors, and irradiationinduced embrittlement and hardening in normal operational conditions are of paramount concern.…”
Section: Introductionmentioning
confidence: 99%