A Review of Hydride Reorientation in Zirconium Alloys for Water-Cooled Reactors

Plyasov, A. A.; Новиков, В. В.; Devyatko, Yu. N.

doi:10.1134/s1063778820090197

Cited by 10 publications

(4 citation statements)

References 27 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It can be observed that the non-hydrotreated sample exhibits minimal detection of zirconium hydride, indicating a low hydrogen content. Conversely, the hydrogenated samples display elongated strip-like hydrides that are predominantly parallel to each other [ 17 , 18 , 19 ], with a uniform distribution throughout the alloy. For further analysis of the morphology and crystal structure of hydrogenated zirconium, Figure 2 illustrates results obtained from a high-hydrogen sample.…”

Section: Resultsmentioning

confidence: 99%

“…The growth kinetics of zirconium alloy oxide film can be divided into two stages: before the transition, the corrosion rate is low and follows an approximately cubic weight gain curve; after the transition, there is an increase in corrosion rate and a shift towards an approximately linear weight gain curve [23]. It was observed that hydrogenation advanced the transition time for these samples, indicating that it accelerates Zircaloy-4's Conversely, the hydrogenated samples display elongated strip-like hydrides that are predominantly parallel to each other [17][18][19], with a uniform distribution throughout the alloy. For further analysis of the morphology and crystal structure of hydrogenated zirconium, Figure 2 illustrates results obtained from a high-hydrogen sample.…”

Section: Effect Of Hydrogenation On the Corrosion Kinetics Of Zircaloy-4mentioning

confidence: 98%

See 1 more Smart Citation

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

Yue,

Zhou,

Zhao

et al. 2024

Materials

View full text Add to dashboard Cite

Hydrogen plays an important role in the corrosion of zirconium alloys, and the degree of influence highly depends on the alloy composition and conditions. In this work, the effects of hydrogenation on the corrosion behavior of Zircaloy-4 in water containing 3.5 ppm Li + 1000 ppm B at 360 °C/18.6 MPa were investigated. The results revealed that hydrogenation can shorten the corrosion transition time and increase the corrosion rates of Zircaloy-4. The higher corrosion rates can be ascribed to the larger stress in the oxide film of hydrogenated samples, which can accelerate the evolution of the microstructure of the oxide film. In addition, we also found that hydrogenation has little effect on the t-ZrO2 content in the oxide film and there is no direct correspondence between the t-ZrO2 content and the corrosion resistance of the Zircaloy-4.

show abstract

Section: Resultsmentioning

confidence: 99%

Section: Effect Of Hydrogenation On the Corrosion Kinetics Of Zircaloy-4mentioning

confidence: 98%

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

Yue,

Zhou,

Zhao

et al. 2024

Materials

View full text Add to dashboard Cite

show abstract

“…As mentioned above, circumferential hydrides can seriously damage the mechanical properties of the matrix only at high hydrogen concentrations or with localized precipitation [ 147 ]. In particular, the fractographs of Zircaloy materials containing circumferential hydrides and radial hydrides are quite different ( Figure 12 a,b) [ 154 , 155 , 156 , 157 , 158 , 159 , 160 ]. The fracture surface displayed in Figure 12 a has a quasi-cleavage fracture of micropores, cavities, and facets [ 155 ].…”

Section: Hydride-induced Embrittlementmentioning

confidence: 99%

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

Jia

Han

2023

Materials

View full text Add to dashboard Cite

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.

show abstract

“…Nuclear fuel cladding zirconium tube is considered as the rst safe line of defense in the nuclear power plant, therefore the demands for wall thickness uniformity of cross sections and the surface quality of zirconium alloy tubes during a series of processing have increased markedly in recent years [5][6][7]. In addition, the adverse working conditions (high temperature and high pressure, neutron radiation and iodine vapor corrosion) will result in the localized corrosion damages of the tubes and abnormal operation of the nuclear power plant, even causing a nuclear leakage [8][9][10][11][12][13][14]. Thus considerable attention should be paid to a suitable measuring method to primarily assure the uniform wall thickness of cross sections in the processing of zirconium alloy tubes.…”

Section: Introductionmentioning

confidence: 99%

A Precision Grinding Technology for Zirconium Alloy Tubes Based on Ultrasonic Wall Thickness Automatic Measurement System

Lai

Wang

et al. 2021

Preprint

View full text Add to dashboard Cite

To ensure the safety and long-term performance of nuclear fuel cladding zirconium tubes, the wall thickness uniformity of each cross section is strictly needed. Therefore, this paper presents comprehensive investigations on development of an automatic ultrasonic wall thickness measurement system for detecting the nuclear zirconium tubes. Based on the determination of overall scheme, optimization of key mechanical structures and design of control system, a series of performance testing analyses of this developed auto-measuring system were performed from aspects of measuring accuracy, measuring efficiency, stability and practicability. The results revealed that it could accurately obtain the wall thickness distribution and effectively guide the subsequent grinding process by automatically generated deviation correcting procedures to achieve the requirement of the wall thickness uniformity. The new combination method of ultrasonic auto-measuring and numerical control grinding proposed in this work would have a great significance for the development and application of nuclear reaction zirconium alloy container.

show abstract

A Review of Hydride Reorientation in Zirconium Alloys for Water-Cooled Reactors

Cited by 10 publications

References 27 publications

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

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

A Precision Grinding Technology for Zirconium Alloy Tubes Based on Ultrasonic Wall Thickness Automatic Measurement System

Contact Info

Product

Resources

About