Raman imaging in corrosion science: High‐temperature oxidation of the zirconium alloys used in the nuclear industry as an example

Author(s):  
Michel Mermoux ◽  
Christian Duriez
2019 ◽  
Author(s):  
Alexander Vasiliev

Abstract Currently, the comprehension among the specialists and functionaries is getting stronger that the nuclear industry can encounter serious difficulties in development in the case of insufficiently decisive measures to enhance the safety level of nuclear objects. The keen competition with renewable energy sources like wind, solar or geothermal energy takes place presently and is expected to continue in future decades. One of main measures of nuclear safety enhancement could be the drastic renovation of materials used in nuclear industry. The analytical models of high-temperature oxidation of new perspective materials including chromium-nickel-based alloys, zirconium-based cladding with protective chromium coating, FeCrAl alloys and composite claddings on the basis of SiC/SiC in the course of design-basis and beyond-design-basis accidents at nuclear power plants (NPPs) are developed and implemented to severe accident computer running code. The comparison with available experimental data is conducted. The preliminary calculations of nuclear pressurized water reactor loss-of-coolant accidents with new types of claddings demonstrate encouraging results for hydrogen generation rate and integral hydrogen production. It looks optimistic for considerable upgrade of safety level for future generation NPPs using new fuel and cladding materials.


2015 ◽  
Vol 465 ◽  
pp. 400-406 ◽  
Author(s):  
А.S. Kuprin ◽  
V.А. Belous ◽  
V.N. Voyevodin ◽  
V.V. Bryk ◽  
R.L. Vasilenko ◽  
...  

2020 ◽  
Vol 28 ◽  
pp. 8-14
Author(s):  
Adéla Chalupová ◽  
Martin Steinbrück ◽  
Mirco Grosse ◽  
Jakub Krejčí ◽  
Martin Ševeček

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.


2014 ◽  
Vol 896 ◽  
pp. 617-620 ◽  
Author(s):  
Bernardus Bandriyana ◽  
Djoko Hadi Prajitno ◽  
Arbi Dimyati

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.


2011 ◽  
Vol 172-174 ◽  
pp. 652-657 ◽  
Author(s):  
Caroline Toffolon-Masclet ◽  
Clara Desgranges ◽  
Carolina Corvalan-Moya ◽  
Jean Christophe Brachet

The EKINOX numerical code, formerly developed to simulate high temperature oxidation of Ni alloys, has been recently adapted to solve out the issue of high temperature oxidation of Zirconium alloys. This numerical code is a one dimensional model that simulates the growth of an oxide layer using a specific algorithm for moving boundaries problem. In order to simulate the oxygen diffusion inside Zr alloys, an adaptation of the EKINOX code was necessary. It consisted in adding, first, a non-null oxygen equilibrium concentration in the substrate and second, a new interface in order to simulate the β/α(O) phase transformation due to oxygen diffusion. In this study, EKINOX has also been coupled with the thermodynamic database for zirconium alloys ZIRCOBASE (thermocalc formalism) in order to obtain accurate concentrations values in each phases (considering local equilibrium at each interface). The present paper illustrates the simulation ability of the code by comparing experimental and calculated oxygen diffusion profiles corresponding to different cases, from isothermal oxidations at high temperature (900 < T < 1250°C) to the study of dissolution kinetics of a pre-transient oxide layer under a neutral environment. The influence of pre-hydriding from a few hundreds up to thousands weight-ppm is also derived from the calculations.


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