Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings

Куприн, А.С.; Белоус, В.А.; Voyevodin, V.N.; Василенко, Р.Л.; Овчаренко, В.Д.; Tolstolutskaya, G.D.; Kopanets, I.E.; Kolodiy, I. V.

doi:10.1016/j.jnucmat.2018.07.063

Cited by 60 publications

(19 citation statements)

References 25 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Additionally, a Cr coating was found to enhance the chemical resistance of the Zr alloy to an environment of primary cooling water, which improved the flexibility of operations under current water chemistry limitations [18]. The results of ion irradiation and neutron irradiation tests have shown that Cr coatings with body centered cubic (BCC) structures have a certain irradiation stability [105,106]; those prepared via the cold spraying method, especially, exhibited irradiation damage resistance [107]. The overall assessment of Cr coatings in ex-situ conditions, i.e., out of a reactor, confirmed their good adhesion, which helps to maintain the integrity of the coating during normal operations.…”

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

“…At present, the most extensively used preparation methods of the Cr-based coatings on Zr alloys are physical vapor deposition (PVD) [14,[18][19][20]22,23,55,[104][105][106]108,109,115,116], cold spraying (CS) [15,24,73,95,107,[117][118][119], and 3D laser melting and coating (3D-LMC) [6,17,25,33,34,69,120]; each are currently used by CEA (French Alternative Energies and Atomic Energy Commission) in France, Westinghouse Electric Corporation in the US, and KAERI in South Korea, respectively. These preparation methods and the characteristics of the prepared coatings are described in the next section.…”

Section: Preparation Of Cr-based Coatingsmentioning

confidence: 99%

See 1 more Smart Citation

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

2020

View full text Add to dashboard Cite

To cope with the shortcomings of nuclear fuel design exposed during the Fukushima Nuclear Accident, researchers around the world have been directing their studies towards accident-tolerant fuel (ATF), which can improve the safety of fuel elements. Among the several ATF cladding concepts, surface coatings comprise the most promising strategy to be specifically applied in engineering applications in a short period. This review presents a comprehensive introduction to the latest progress in the development of Cr-based surface coatings based on zirconium alloys. Part I of the review is a retrospective look at the application status of zirconium alloy cladding, as well as the development of ATF cladding. Following this, the review focuses on the selection process of ATF coating materials, along with the advantages and disadvantages of the current mainstream preparation methods of Cr-based coatings worldwide. Finally, the characteristics of the coatings obtained through each method are summarized according to some conventional performance evaluations or investigations of the claddings. Overall, this review can help assist readers in getting a thorough understanding of the selection principle of ATF coating materials and their preparation processes.

show abstract

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

Section: Preparation Of Cr-based Coatingsmentioning

confidence: 99%

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

2020

View full text Add to dashboard Cite

show abstract

“…In the high-temperature oxidation environment of the reactor, the oxidation resistance of the ATF cladding depends on the formation of attached, non-volatile, and crack-free oxide scale. Nowadays, Cr is considered an ideal material to study as a hard protective coating with high hardness, corrosion resistance, and oxidation resistance [4][5][6][7][8]. There have been extensive studies on the oxidation resistance of Cr coatings under LOCA conditions.…”

Section: Introductionmentioning

confidence: 99%

Effect of Al Content on the High-Temperature Oxidation Resistance and Structure of CrAl Coatings

Meng

Wang

et al. 2021

Coatings

View full text Add to dashboard Cite

The oxidation behaviors of Cr, Cr93.4Al6.6, Cr58.1Al41.9, and Cr34.5Al65.5 coatings, deposited by using multi-arc ion plating technology, at high temperature were studied. The weight gain, oxide thickness, morphology, and phase composition of the coatings before and after oxidation were analyzed in detail. The results show that there is an Al content window available for tuning the oxidation behaviors of the CrAl-based coatings. The Cr93.4Al6.6 coating is considered to be most protective and can effectively improve the high-temperature oxidation resistance of the substrate; whereas, too high an Al content has a harmful effect on the antioxidant properties of the coatings. The oxidation mechanism of Cr and CrAl coatings were also discussed.

show abstract

“…The deposition of protective coatings having a high oxidation resistance onto the fuel elements is an expedient solution of this problem [2]. The results of experiments have shown that from a variety of protective coatings just chromium coatings possess desired properties (resistance to oxidation, corrosion and irradiation) [3][4][5]. Therefore, of special importance is to investigate the effect of chromium coatings on the mechanical properties of zirconium tubes at different test temperatures and to find out the causes of structural material degradation during the long reactor operation.…”

Section: Introductionmentioning

confidence: 99%

EFFECT OF CHROMIUM COATINGS ON THE MECHANICAL PROPERTIES OF Zr1Nb FUEL CLADDINGS IN LONGITUDINAL AND TRANSVERSE DIRECTIONS

Белоус¹,

Voyevodin²,

Gozhenko³

et al. 2019

Problems of Atomic Science and Technology

Self Cite

View full text Add to dashboard Cite

This study was aimed at investigating the chromium coating effect on the mechanical properties of Zr1Nb fuel claddings in the case of a tensile fracture in longitudinal and transverse directions at temperatures of 20 and 350 °С. Tests were carried out using the samples of a similar shape, namely, with an equal test portion length that is important for comparison of results. The obtained results have shown that at a test temperature of 20 °С the mechanical properties of initial samples are higher in the longitudinal direction than in the transverse direction. The ductility is slightly higher at T = 350 °С in the longitudinal direction, and σ0.2 and σв are practically equal. The preliminary deformation of ring samples increases their ductility from 23 to 34% independently on the test temperature. Deposition of the chromium coatings on the samples leads to the slight increase of mechanical properties in the transverse direction and decrease of σ0.2 with unchanged σв and δ% in the longitudinal direction at the room test temperature, and at 350 °С it practically do not change the properties of coated samples in both the directions except the ring sample ductility decrease.

show abstract

Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings

Cited by 60 publications

References 25 publications

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

Effect of Al Content on the High-Temperature Oxidation Resistance and Structure of CrAl Coatings

EFFECT OF CHROMIUM COATINGS ON THE MECHANICAL PROPERTIES OF Zr1Nb FUEL CLADDINGS IN LONGITUDINAL AND TRANSVERSE DIRECTIONS

Contact Info

Product

Resources

About