Download or read book Understanding Corrosion and Hydrogen Pickup of Zirconium Fuel Cladding Alloys written by Jing Hu and published by . This book was released on 2018 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, and porosity in zirconium alloys at different stages of oxidation. Samples from both autoclave and in-reactor conditions were available, including ZIRLOTM, Zr-1.0Nb, and Zr-2.5Nb samples with different heat treatments. Scanning transmission electron microscopy (STEM), transmission Kikuchi diffraction (TKD), and automated crystal orientation mapping with TEM were used to study the grain structure and phase distribution. Significant differences in grain morphology were observed between samples oxidized in the autoclave and in-reactor, with shorter, less well-aligned monoclinic grains and more tetragonal grains in the neutron-irradiated samples. A combination of energy-dispersive X-ray mapping in STEM and atom probe tomography analysis of second-phase particles (SPPs) can reveal the main and minor element distributions respectively. Neutron irradiation seems to have little effect on promoting fast oxidation or dissolution of ?-niobium precipitates but encourages the dissolution of iron from Laves-phase precipitates. An electron energy-loss spectroscopy (EELS) analysis of the oxidation state of niobium in ?-niobium SPPs in the oxide revealed the fully oxidized Nb5+ state in SPPs deep into the oxide but Nb2+ in crystalline SPPs near the metal-oxide interface. EELS analysis and automated crystal orientation mapping with TEM revealed Widmanstatten-type suboxide layers in some samples with the hexagonal ZrO structure predicted by ab initio modeling. The combined thickness of the ZrO suboxide and oxygen-saturated layers at the metal-oxide interface correlated well to the instantaneous oxidation rate, suggesting that this oxygen-rich zone is part of the protective oxide that is rate limiting in the transport processes involved in oxidation. Porosity in the oxide had a major influence on the overall rate of oxidation, and there was more porosity in the rapidly oxidizing annealed Zr-1.0Nb alloy than in either the recrystallized alloy or the similar alloy exposed to neutron irradiation.

Download or read book The Role of Nickel in Hydrogen Pick up During In reactor Corrosion of Zirconium Alloys written by Aditya Shivprasad and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Hydrogen pick-up of zirconium-based fuel cladding and structural materials duringin-reactor corrosion can degrade fuel component performance in existing light waterreactors (LWRs) and advanced nuclear reactors, such as the LWR-like supercriticalwater reactors (SCWRs), as the ingress of corrosion hydrogen can lead to the formationof brittle hydrides. In the boiling water reactor (BWR) environment, Zircaloy-2 fuelcladding and reactor core components, such as water rods and channel boxes, canexperience accelerated hydrogen pick-up (higher pickup fraction) at high burnup whenexposed for one extra 24-month cycle, while Zircaloy-4 components under similarconditions do not. Because the principal difference between the two alloys is thatZircaloy-2 contains nickel, this accelerated hydrogen pick-up has been hypothesizedto result from the presence of nickel and its role in the corrosion process whenincorporated into the protective oxide layer.Zircaloy-2 and Zircaloy-4 sister samples were corroded in 360 _C water and anadditional set of Zircaloy-2 samples was corroded in 400 _C steam. Total weightgain, assumed to be due mostly to oxygen, and hydrogen content were measured asfunctions of exposure time. The results indicate that Zircaloy-2 samples absorbed morehydrogen than did Zircaloy-4 samples on the basis of total weight gain (hydrogen pickupfraction), though both exhibited similar corrosion kinetics parameters. Microbeamsynchrotron radiation X-ray absorption near-edge spectroscopy (XANES) of selectedZircaloy-2 samples at the Advanced Photon Source (APS) was used to probe theoxidation states of nickel and iron in these materials and understand the evolutionof the oxidation states of these alloying elements as functions of distance from theoxide/metal interface. Result showed that a significant fraction of nickel atomsremained metallic upon incorporation in the oxide layer. In contrast, iron atomsoxidized much earlier than did nickel atoms and, in most cases, fully oxidized withinseveral micrometers from the oxide/metal interface. A general hypothesis was madethat metallic nickel in contact with the coolant may catalyze the surface reactionsinvolved in the hydrogen pick-up mechanism.To understand accelerated hydrogen pick-up of certain Zircaloy-2 samples at highburn-up, additional XANES examinations were performed on Zircaloy-2 water rodsexposed in-reactor to high burn-up in commercial BWRs. The first set of samples wascorroded in the Limerick-1 reactor, while the second set was corroded in the Dresden-2reactor. Within each set of samples, fluences, oxide thicknesses, and sample elevationswere similar, but hydrogen pick-up fractions were vastly different. In the first setof samples, oxide thicknesses ranged from 28 - 35 m, but hydrogen pick-up rangedbetween 15 and 51%. In the second set of samples, oxide thicknesses ranged between3.5 m and 16 m, but hydrogen pick-up ranged from 28 - 69%. All samples wereirradiated to fluences between 9.4 and 13.1 1021 n/cm2 for neutron energies above1 MeV. Results of XANES examinations showed a similar correlation between thedelayed oxidation of nickel and higher hydrogen pick-up of Zircaloy-2 at high burn-up.A significant fraction (greater than 30%) of nickel atoms were found to be in themetallic state in the porous oxide layer. It was hypothesized that this metallic nickelis responsible for enhancing hydrogen pick-up by catalyzing the surface reactions thataffect the overall hydrogen pick-up reaction. This would allow for easier absorptionof hydrogen into the protective oxide layer from the coolant. Ab initio modeling ofXANES of selected iron- and nickel-containing compounds was also performed andcompared to experimental results to help understand how different populations ofalloying elements oxidized upon incorporation into the oxide layer.A concurrent study of the microstructure of oxide layers formed on these sameirradiated water rods was performed to understand if there was a characteristicmicrostructure associated with accelerated hydrogen pick-up. Microbeam X-raydiffraction (XRD) at the APS was performed on water rod samples to study oxidetexture, phase content, and grain size. A similar examination was performed onsteam-corroded Zircaloy-2 to serve as a comparison. Results showed that the oxidelayers formed on these samples consisted primarily of highly-oriented monoclinic phasezirconium oxide with a small fraction of tetragonal phase oxide. Monoclinic phasegrains were shown to grow as a function of distance from the oxide/metal interface,while tetragonal phase grains remained a constant size, indicating a tetragonal-to-monoclinic phase transformation above a critical grain size of approximately 10 nm.The tetragonal phase fraction was also calculated and observed to maximize nearthe oxide/metal interface, coinciding with the appearance of the (002)-tetragonalphase diffraction reflection, which appeared to be highly-oriented and strained, butdisappeared away from the oxide/metal interface. Findings were consistent withprevious microbeam XRD examinations of oxide layers formed on Zircaloy-4 underautoclave conditions. Transmission XRD examinations were also performed on aselected steam-corroded sample to serve as an additional comparison.The observations presented in this study helped to propose a mechanism foroxidation of different populations of iron and nickel upon incorporation into theZircaloy-2 oxide layer and the effect on the hydrogen pick-up mechanism.

Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 1996 with total page 907 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance written by Arthur T. Motta and published by . This book was released on 2018 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt: A review is presented of work performed in our group over the years in the areas of radiation damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium alloy nuclear fuel cladding with the goal of developing a greater mechanistic understanding of cladding performance in service.

Download or read book Hydrogen Pickup During Corrosion of Zirconium Alloys written by Warren E. Berry and published by . This book was released on 1959 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Specific Zirconium Alloy Design Program Quarterly Progress Report written by and published by . This book was released on 1962-02 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 2000 with total page 953 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Hydrogen Pickup Mechanism in Zirconium Alloys written by Adrien Couet and published by . This book was released on 2018 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: Because hydrogen ingress into zirconium cladding can cause embrittlement and limit cladding lifetime, hydrogen pickup during corrosion is a critical life-limiting degradation mechanism for nuclear fuel. However, mechanistic knowledge of the oxidation and hydrogen pickup mechanisms is still lacking. In an effort to develop such knowledge, we conducted a comprehensive study that included detailed experiments combined with oxidation modeling. We review this set of results conducted on zirconium alloys herein and articulate them into a unified corrosion theoretical framework. First, the hydrogen pickup fraction (fH) was accurately measured for a specific set of alloys specially designed to determine the effects of alloying elements, microstructure, and corrosion kinetics on fH. We observed that fH was not constant and increased until the kinetic transition and decreased at the transition. fH depended on the alloy and was lower for niobium-containing alloys. These results led us to hypothesize that hydrogen pickup during corrosion results from the need to balance the charge during the corrosion reaction such that fH decreases when the rate of electron transport through the protective oxide increases. To assess this hypothesis, two experiments were performed: (1) micro-X-ray absorption near-edge spectroscopy (?-XANES) to investigate the evolution of the oxidation state of alloying elements when incorporated in the growing oxide and (2) in situ electrochemical impedance spectroscopy (EIS) to measure oxide resistivity as a function of exposure time on different alloys. With the use of these results, we developed an analytical zirconium alloy corrosion model based on the coupling of oxygen vacancies and electron currents. Both modeling and EIS results show that as the oxide electric conductivity decreases the fH increases. These new results support the general hypothesis of charge balance. The model quantitatively and qualitatively predicts the differences observed in oxidation kinetics and hydrogen pickup fraction between different alloys.

Download or read book Hydrogen and Oxygen Distribution During Corrosion of Zirconium Alloy Nuclear Fuel Cladding written by Christopher Jones and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Corrosion and Hydrogen Pickup Mechanisms of Zirconium Alloys written by Sylvester Brian Setiadinata and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Download or read book Corrosion of Zirconium Alloys written by and published by . This book was released on 1964 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by and published by ASTM International. This book was released on with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Hydrogen Entry in Zircaloy 4 Fuel Cladding written by Jennifer Anne Jarvis and published by . This book was released on 2015 with total page 318 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion and hydrogen pickup of zirconium alloy fuel cladding in water cooled nuclear reactors are life-limiting phenomena for fuel. This thesis studies the fate of hydrogen liberated by waterside corrosion of Zircaloy-4 fuel cladding in Pressurized Water Reactors (PWRs): are the adsorbed protons incorporated into the oxide and eventually the metal, or are they evolved into molecular hydrogen and released into the coolant? Water chemistry modeling was used to understand effects of radiolysis and CRUD. Density functional theory (DFT) was used to investigate the role of oxidized Zr(Fe,Cr)2 second phase particles. Chemical potentials and the electron chemical potential were used to connect these two modeling efforts. A radiolysis model was developed for the primary loop of a PWR. Dose profiles accounting for fuel burnup, boron addition, axial power profiles, and a CRUD layer were produced. Dose rates to the bulk coolant increased by 21-22% with 12.5-75 pim thick CRUD layers. Radially-averaged core chemistry was compared to single-channel chemistry at individual fuel rods. Calculations showed that local chemistry was more oxidizing at high-power fuel and fuel with CRUD. Local hydrogen peroxide concentrations were up to 2.5 ppb higher than average levels of 5-8 ppb. Radiolysis results were used to compute chemical potentials and the corrosion potential. Marcus theory was applied to compare the band energies of oxides associated with Zircaloy-4 and the energy levels for proton reduction in PWR conditions. Hydrogen interactions with Cr203 and Fe203, both found in oxidized precipitates, were studied with DFT. Atomic adsorption of hydrogen was modeled on the Cr and Feterminated (0001) surfaces. Climbing Image-Nudged Elastic Band calculations were used to model the competing pathways of hydrogen migration into the subsurface and molecular hydrogen formation. A two-step mechanism for hydrogen recombination was identified consisting of: reduction of an adsorbed proton (H+) to a hydride ion (H-) and H2 formation from an adjacent adsorbed proton and hydride ion. Overall, results suggest that neither surface will be an easy entrance point for hydrogen ingress and that Cr203 is more likely to be involved in hydrogen evolution than the Fe203.

Download or read book Hydrogen Pickup Mechanism of Zirconium Alloys written by Adrien Couet and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Although the optimization of zirconium based alloys has led to significant improvements in hydrogen pickup and corrosion resistance, the mechanisms by which such alloy improvements occur are still not well understood. In an effort to understand such mechanisms, a systematic study of the alloy effect on hydrogen pickup is conducted, using advanced characterization techniques to rationalize precise measurements of hydrogen pickup. The hydrogen pick-up fraction is accurately measured for a specially designed set of commercial and model alloys to investigate the effects of alloying elements, microstructure and corrosion kinetics on hydrogen uptake. Two different techniques to measure hydrogen concentrations were used: a destructive technique, Vacuum Hot Extraction, and a non-destructive one, Cold Neutron Prompt Gamma Activation Analysis. The results indicate that hydrogen pickup varies not only from alloy to alloy but also during the corrosion process for a given alloy. For instance Zircaloy type alloys show high hydrogen pickup fraction and sub-parabolic oxidation kinetics whereas ZrNb alloys show lower hydrogen pickup fraction and close to parabolic oxidation kinetics. Hypothesis is made that hydrogen pickup result from the need to balance charge during the corrosion reaction, such that the pickup of hydrogen is directly related to (and indivisible of) the corrosion mechanism and decreases when the rate of electron transport or oxide electronic conductivity through the protective oxide increases. According to this hypothesis, alloying elements (either in solid solution or in precipitates) embedded in the oxide as well as space charge variations in the oxide would impact the hydrogen pick-up fraction by modifying electron transport, which drives oxidation and hydriding kinetics. Dedicated experiments and modelling were performed to assess and validate these hypotheses.In-situ electrochemical impedance spectroscopy (EIS) experiments were performed on Zircaloy-4 tubes to directly measure the evolution of oxide electronic conductivity as function of exposure time. The results show that oxide electronic conductivty decreases as function of exposure time and that its variations are directly correlated to the instantaneous hydrogen pickup fraction variations. The electron transport through the oxide layer is thus altered as the oxide grows, reasons for which are yet to be exactly determined. Preliminary results also show that oxide electronic conductivty of ZrNb alloys would be much higher compared with Zircaloy-4. Thus, it is confirmed that oxide electronic conductivity is a key parameter in the hydrogen and oxidation mechanism.Because the mechanism whereby alloying elements are incorporated into the oxide layer is critical to changing [sigma]_(e^-)^ox, the evolution of the oxidation state of two common alloying elements, Fe and Nb, when incorporated into the growing oxide layers is investigated using X-Ray Absorption Near-Edge Spectroscopy (XANES) using micro-beam synchrotron radiation on cross sectional oxide samples. The results show that the oxidation of both Fe and Nb is delayed in the oxide layer compared to that of Zr, and that this oxidation delay is related to the variations of the instantaneous hydrogen pick-up fraction with exposure time. The evolution of Nb oxidation as function of oxide depth is also compatible with space charge compensation in the oxide and with an increase in oxide electronic conductivity of ZrNb alloys compared to Zircaloys.Finally, various successively complex models from the well-known Wagner oxidation theory to the more complex effect of space charge on oxidation kinetics have been developed. The general purpose of the modeling effort is to provide a rationale for the sub-parabolic oxidation kinetics and demonstrate the correlation with hydrogen pickup fraction. It is directly demonstrated that parabolic oxidation kinetics is associated with high oxide electronic conductivity and low space charges in the oxide whereas sub-parabolic oxidation kinetics is associated with lower oxide electronic conductivity and higher space charge in the oxide.All these observations helped us to propose a general corrosion mechanism of zirconium alloys involving both oxidation and hydrogen pickup mechanism to better understand and predict the effect of alloying additions on the behavior of zirconium alloys.

Download or read book Zirconium in the Nuclear Industry Tenth International Symposium written by A. M. Garde and published by ASTM International. This book was released on 1994 with total page 805 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Out of Reactor Test of Corrosion and Hydrogen Pickup in Fuel Cladding Materials in Contact with Nickel Metal written by Daniel M. Wells and published by . This book was released on 2018 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: Increased reactor coolant hydrogen concentration in pressurized water reactors (PWRs) is under consideration for potential benefits in reducing primary water stress corrosion cracking (PWSCC) crack growth rate as well as increasing PWSCC crack initiation time in nickel-based alloys. Potential concerns related to fuel performance include possible increases in hydrogen pickup (HPU) by zirconium-based alloys and the enhancement of the pickup through the so-called nickel-window effect. Although the risk of this occurrence may be low, the consequences of increased HPU could be substantial. We examined the impact of dissolved hydrogen (DH) concentrations on Zircaloy-4 corrosion and HPU when the samples are in contact with nickel sources. The work was completed in conjunction with a large project that evaluated the impact of dissolved hydrogen on various fuel cladding and spacer weld specimens of M5®, ZIRLO®, Optimized ZIRLOTM, Low-Tin ZIRLOTM, Optimized Low-Tin Zircaloy-4, and Zircaloy-2 in either as-received or pre-oxidized conditions for exposures up to 730 days in high-pressure, out-of-reactor autoclave systems operating with a simulated PWR coolant at three different DH concentrations: 30, 100, and 500 cm3 (cc) H2/kg H2O. A significant increase in HPU was observed for some Zircaloy-4 specimens in contact with synthetic crud at elevated DH levels. The HPU increased with increasing DH and a metallic nickel fraction in the synthetic crud. The formation of metallic nickel in the synthetic crud samples at elevated DH levels was confirmed.