Polycrystalline Diamond Films as Protection of Zircaloy Fuel Cladding

2014 ◽  
Author(s):  
Jan Škarohlíd ◽  
Radek Škoda
Keyword(s):  
High Temperature ◽  
Ion Beam ◽  
Cooling Water ◽  
Chemical Vapor ◽  
Polycrystalline Diamond ◽  
Zirconium Alloys ◽  
Carbon Layer ◽  
Primary Circuit ◽  
Temperature Oxidation ◽  
Diamond Layer

Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys. Zirconium alloys are used as cladding material in almost all types of nuclear reactors, where creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper Zircaloy-2 alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations were done for zirconium alloy covered with diamond layer before and after corrosion and irradiation tests - ion beam irradiation tests and high temperature steam exposure.

High Temperature Oxidation of Polycrystalline Diamond Coated Zirconium Alloy

2016 ◽  
Author(s):  
Jan Škarohlíd ◽  
Radek Škoda ◽  
Irena Kratochvílová
Keyword(s):  
Raman Spectroscopy ◽  
High Temperature ◽  
Zirconium Alloy ◽  
High Temperature Oxidation ◽  
Polycrystalline Diamond ◽  
Zirconium Alloys ◽  
Hydrogen Release ◽  
Primary Circuit ◽  
Temperature Oxidation ◽  
Diamond Layer

Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys and decrease corrosion rate of zirconium alloy during standard operation. Zirconium alloys are widely used as cladding and construction material in almost all types of nuclear reactors, where usually creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper zirconium alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations (Raman spectroscopy) were done for zirconium alloy covered with polycrystalline diamond layer before and after high temperature steam exposure. Weight increase and hydrogen release ware measured during steam exposure.

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air

2015 ◽  
Vol 465 ◽  
pp. 400-406 ◽  
Author(s):  
А.S. Kuprin ◽  
V.А. Belous ◽  
V.N. Voyevodin ◽  
V.V. Bryk ◽  
R.L. Vasilenko ◽  
...  
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Zirconium Alloys ◽  
Vacuum Arc ◽  
Temperature Oxidation ◽  
Oxidation In Air

scholarly journals HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY

2020 ◽  
Vol 28 ◽  
pp. 8-14
Author(s):  
Adéla Chalupová ◽  
Martin Steinbrück ◽  
Mirco Grosse ◽  
Jakub Krejčí ◽  
Martin Ševeček
Keyword(s):  
High Temperature ◽  
Melting Point ◽  
High Temperature Oxidation ◽  
Zirconium Alloys ◽  
Temperature Oxidation ◽  
Ni Alloy ◽  
Institute Of Technology ◽  
Kinetics Of ◽  
Karlsruhe Institute ◽  
Nuclear Applications

The investigations in this paper deal with the Cr-Ni alloy. The material has been recently proposed as a potential ATF concept, primarily due to its behaviour under high-temperature oxidation. A set of experiments to determine the melting point and describe the oxidation kinetics of the Cr-Ni alloy were performed in Karlsruhe Institute of Technology. Presented results reveal its superb oxidation resistance comparing to zirconium alloys. Therefore, the alloy has a great potential for nuclear applications.

scholarly journals High Temperature Anti-Oxidation Behavior and Mechanical Property of Radio Frequency Magnetron Sputtered Cr Coating

Metals ◽  
2020 ◽  
Vol 10 (11) ◽  
pp. 1509
Author(s):  
Guangbin Li ◽  
Yanhong Liu ◽  
Yingchun Zhang ◽  
Huailin Li ◽  
Xiaojing Wang ◽  
...  
Keyword(s):  
High Temperature ◽  
Radio Frequency ◽  
Oxidation Behavior ◽  
Zirconium Alloys ◽  
Rf Magnetron Sputtering ◽  
X Ray Diffraction ◽  
Temperature Oxidation ◽  
High Temperature Steam ◽  
High Temperature Oxidation Behavior ◽  
Cr Coating

A dense and uniform Cr coating was fabricated on the zirconium alloys fuel claddings by radio frequency (RF) magnetron sputtering to improve the mechanical and anti-oxidation properties under 1200 °C steam environment. The phase composition and the micro and macro morphologies of the specimens were investigated by X-ray diffraction (XRD), energy dispersive spectroscopy (EDS), scanning electron microscope (SEM) and optical-microtopography (OM) analyses, and the high-temperature oxidation behavior was evaluated at 1200 °C steam environment for 3000 s. In this paper, there exists a positive correlation between thickness and Vickers hardness (HV), and a negative correlation between surface roughness and bonding force. Radial tensile was introduced to investigate the deformation-resistant performance, and the displacement of the Cr-coated specimen was as low as 2.32 mm, which was much lower than the uncoated zircaloy cladding (3.05 mm). Different thicknesses of Cr coatings were deposited to investigate the oxidation degrees of zircaloy cladding under a high-temperature steam environment. The optimal 6 μm Cr-coated zirconium alloys cladding exhibited an excellent anti-oxidation property, and the weight gain was as low as ~4.12 mg/cm2, which was almost one-third of the uncoated specimen.

Effect of Copper Addition on the High Temperature Oxidation of Zirconium Alloy ZrNbMoGe for Advanced Reactor Fuel Cladding Material

2014 ◽  
Vol 896 ◽  
pp. 617-620 ◽  
Author(s):  
Bernardus Bandriyana ◽  
Djoko Hadi Prajitno ◽  
Arbi Dimyati
Keyword(s):  
High Temperature ◽  
Zirconium Alloy ◽  
High Temperature Oxidation ◽  
Zirconium Alloys ◽  
Magnetic Suspension ◽  
Pressurized Water ◽  
Temperature Oxidation ◽  
Copper Addition ◽  
Effect Of Copper ◽  
Cladding Material

The zirconium alloys ZrNbMoGe have been developed with the aim to improve its high temperature oxidation for employment as a cladding material in Pressurized Water Reactor (PWR) and to extend the over all fuel burn-up. In this paper the effect of Cu addition on the high temperature oxidation behavior of ZrNbMoGe alloy was investigated. The zirconium alloy was produced by melting the zirconium-niobium-molybdenum-germanium and copper-sponge in an arc furnace in an argon environment by the temperature higher than 1850C. The weight percentages of the elements were 2.50 wt.% Nb, 0.5 wt.% Mo, 0.1 wt.% Ge, 0.5 wt.% Cu and Zr in balanced. The oxidation test was carried out in the Magnetic Suspension Balance (MSB) workstation. Two specimens of ZrNbMoGe alloys without and with Cu addition were oxidized in atmosphere at temperature of 500 °C and 700 °C for 8 hours. The results show the oxidation kinetics followed the parabolic rate law. The difference of oxidation behaviors of the two specimens were considered to be caused by the formation of different kind of oxide layers due to the Cu addition.

Ion beam mixing effects on the high temperature oxidation resistance of iron and nickel

1985 ◽  
Vol 69 (2) ◽  
pp. 341-349 ◽  
Author(s):  
F. Giacomozzi ◽  
L. Guzman ◽  
A. Molinari ◽  
A. Tomasi ◽  
E. Voltolini ◽  
...  
Keyword(s):  
High Temperature ◽  
Oxidation Resistance ◽  
High Temperature Oxidation ◽  
Ion Beam ◽  
Ion Beam Mixing ◽  
Temperature Oxidation ◽  
Mixing Effects
Sign in / Sign up

Export Citation Format

Share Document