scholarly journals THE CELL FOR ELECTRON IRRADIATION OF STRESSED STEEL SAMPLES IN A SUPERCRITICAL WATER FLOW FOR CORROSION EVALUATION

2019 ◽  
pp. 172-180
Author(s):  
A.S. Bakai ◽  
V.N. Boriskin ◽  
M.I. Bratchenko ◽  
R.N. Dronov ◽  
S.V. Dyuldya ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Electron Irradiation ◽  
Supercritical Water ◽  
Strain State ◽  
Water Coolant ◽  
Hydrodynamic Models ◽  
Corrosion Evaluation ◽  
Irradiation Cell ◽  
Stress Application ◽  
Novel Design

To study experimentally the stress enhanced corrosion of structural materials in a water coolant flow under electron irradiation, a novel design of the target irradiation cell was developed. The stress application scheme is described and the stress-strain state of samples is calculated. Hydraulic resistance of the stainless steel 12X18H10T samples loaded cell has been measured at a dedicated facility and is discussed in terms of hydraulic and hydrodynamic models. System Thermal Hydraulics calculations have shown the device capability to operate efficiently in a natural convection driven Supercritical Water Circulation Loop.

scholarly journals Oxidation Behavior of an Austenitic Steel (Fe, Cr and Ni), the 310 H, in a Deaerated Supercritical Water Static System

Metals ◽  
2021 ◽  
Vol 11 (4) ◽  
pp. 571
Author(s):  
Aurelia Elena Tudose ◽  
Ioana Demetrescu ◽  
Florentina Golgovici ◽  
Manuela Fulger
Keyword(s):  
Stainless Steel ◽  
Supercritical Water ◽  
Nuclear Reactor ◽  
Electrochemical Impedance ◽  
Electrochemical Methods ◽  
Metallographic Analysis ◽  
Gravimetric Analysis ◽  
Static System ◽  
Eis Measurements ◽  
Supercritical Temperature

The aim of this work was to study the corrosion behavior of a Fe-Cr-Ni alloy (310 H stainless steel) in water at a supercritical temperature of 550 °C and a pressure of 250 atm for up to 2160 h. At supercritical temperature, water is a highly aggressive environment, and the corrosion of structural materials used in a supercritical water-cooled nuclear reactor (SCWR) is a critical problem. Selecting proper candidate materials is one key issue for the development of SCWRs. After exposure to deaerated supercritical water, the oxides formed on the 310 H SS surface were characterized using a gravimetric analysis, a metallographic analysis, and electrochemical methods. Gravimetric analysis showed that, due to oxidation, all the tested samples gained weight, and oxidation of 310H stainless steel at 550 °C follows parabolic rate, indicating that it is driven by a diffusion process. The data obtained by microscopic metallography concord with those obtained by gravimetric analysis and show that the oxides layer has a growing tendency in time. At the same time, the results obtained by electrochemical impedance spectroscopy (EIS) measurements indicate the best corrosion resistance of Cr, and (Fe, Mn) Cr2O4 oxides developed on the samples surface after 2160 h of oxidation. Based on the results obtained, a strong correlation between gravimetric analysis, metallographic analysis, and electrochemical methods was found.

Oxidation of 316 stainless steel in supercritical water

2009 ◽  
Vol 51 (5) ◽  
pp. 1069-1072 ◽  
Author(s):  
Mingcheng Sun ◽  
Xinqiang Wu ◽  
Zhaoen Zhang ◽  
En-Hou Han
Keyword(s):  
Stainless Steel ◽  
Supercritical Water ◽  
316 Stainless Steel

Corrosion behavior of a 304-oxide dispersion strengthened austenitic stainless steel in supercritical water

2015 ◽  
Vol 67 (3) ◽  
pp. 264-270 ◽  
Author(s):  
S. F. Li ◽  
Z. J. Zhou ◽  
L. F. Zhang ◽  
L. W. Zhang ◽  
H. L. Hu ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Corrosion Behavior ◽  
Supercritical Water ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion

Corrosion Evaluation of a Navy MK50 Weapon Station Friction Brake Assembly

2020 ◽  
Author(s):  
Ruby Romsland ◽  
Kenneth J. McDonald
Keyword(s):  
Stainless Steel ◽  
Large Scale ◽  
Galvanic Corrosion ◽  
The United States ◽  
Electrochemical Polarization ◽  
Polarization Measurements ◽  
Corrosion Evaluation ◽  
Stainless Steel Screw ◽  
Unknown Composition ◽  
Friction Brake

Abstract The presence of corrosion on or within structures is of major concern as corrosion reduces the integrity of the materials which could potentially result in large-scale failures of structures and equipment.1 The United States Navy is an organization that actively works to prevent large equipment failure due to corrosion. One such problem is the corrosion of the friction brake assembly on the MK50 Weapon Station, which has recently been experiencing corrosion between the friction brake and its set screw preventing it from operating correctly. The friction brake was known to be stainless steel; however, the set screw was of unknown composition. Through elemental analysis it was determined that the MK50 Weapons Station friction brake set screw was similar in composition to commonly available black oxide coated steel screws. Electrochemical polarization measurements of the friction brake assembly components revealed that the set screw and the friction brake were electrochemically dissimilar metals which resulted in the galvanic corrosion of the assembly when out at sea. The electrochemical polarization measurements of a stainless steel screw showed a corrosion potential similar to that of the friction brake; therefore, replacing the current set screw with a stainless steel screw would decrease the galvanic potential difference between the set screw and the friction brake. This proposed solution is expected to slow or prevent further corrosion of the MK50 Weapon Station ensuring the combat readiness of the equipment.

scholarly journals Intergranular corrosion evaluation of friction stir welded AISI 410S ferritic stainless steel

2019 ◽  
Vol 8 (2) ◽  
pp. 1878-1887 ◽  
Author(s):  
Gerbson de Queiroz Caetano ◽  
Cleiton Carvalho Silva ◽  
Marcelo Ferreira Motta ◽  
Hélio Cordeiro Miranda ◽  
Jesualdo Pereira Farias ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Ferritic Stainless Steel ◽  
Intergranular Corrosion ◽  
Friction Stir ◽  
Corrosion Evaluation

Rate Theory for Dislocation Loops Evolution in AL-6XN Austenitic Stainless Steel under Proton Irradiation

2018 ◽  
Vol 913 ◽  
pp. 237-246 ◽  
Author(s):  
Yan Xia Yu ◽  
Li Ping Guo ◽  
Zheng Yu Shen ◽  
Yun Xiang Long ◽  
Zhong Cheng Zheng ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Supercritical Water ◽  
Proton Irradiation ◽  
Theory Model ◽  
Average Density ◽  
Rate Theory ◽  
Dislocation Loops ◽  
Average Size ◽  
Supercritical Water Cooled Reactor

The average size and density evolution of dislocation loops in AL-6XN austenitic stainless steel, a candidate fuel cladding material for supercritical water-cooled reactor, under proton irradiation were simulated through a rate theory model. The simulation results exhibit relatively good agreement with the experimental results at 563 K. The size and density of defect clusters are calculated under irradiation temperature between 550 K and 900 K and irradiation doses up to 15 dpa which satisfies the working condition in supercritical water-cooled reactor. The fast nucleation between self-interstitials happens at the initial stage of irradiation. The average size of dislocation loops increases while the average density of these loops reduces with the increasing temperature, and the average density approaches to a constant when irradiated at higher irradiation doses. The mechanism is discussed based on the variation of rate constants of defect reactions and the variation of the diffusion coefficients of interstitials and dislocation loops with dose and temperature.

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