Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

2021 ◽  
Author(s):  
Toshihide Takai ◽  
Tomohiro Furukawa ◽  
Shigeki Watanabe ◽  
Noriko S. Ishioka
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Target System ◽  
Liquid Lead ◽  
Low Oxygen ◽  
Operation Conditions ◽  
Fecral Alloy ◽  
Liquid Bismuth ◽  
Oxygen Conditions ◽  
Bismuth Target

Abstract For the mass production of astatine-211, a promising radiopharmaceutical for cancer treatment, the National Institute for Quantum and Radiological Science and Technology has proposed the innovative “Liquid Bismuth Target System.” The target window in this system must be made from a material that resists the highly corrosive liquid bismuth environment. To meet this requirement, a promising target window material was selected in corrosion experiments performed in stagnant liquid bismuth. Based on knowledge of corrosion in liquid lead–bismuth eutectic gained during the development of fast reactors and accelerator-driven subcritical systems, FeCrMo–alloy, FeCrAl–alloy, and austenitic stainless steel (as a reference) were selected as the specimen materials. Experiments were carried out under saturated dissolved oxygen and low oxygen conditions, and the corrosion behaviors of the specimens were evaluated, mainly by scanning electron microscopy. The FeCrAl–alloy exhibited the most excellent corrosion resistance, followed by FeCrMo–alloy. Both materials are suitable candidates for the target window. Although austenitic stainless steel was less corrosion resistant than the former two materials, it is a likely applicable for the target window under appropriately limited operation conditions (such as irradiation current and exposure time) of the liquid bismuth target system.

Interaction of Liquid Lead Bismuth and Materials in Spallation Target

2021 ◽  
Vol 1024 ◽  
pp. 27-40
Author(s):  
Kenji Kikuchi
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ultrasonic Waves ◽  
Liquid Lead ◽  
Spallation Target ◽  
Nuclear Transmutation ◽  
Proton Current ◽  
Electromagnetic Fluid ◽  
Cold Worked ◽  
Flowing System

Material choices for liquid lead bismuth spallation target are some of austenitic stainless steel, ferrite martensitic steel and cold-worked austenitic stainless steel. In order to ensure materials resistance to irradiation and corrosion as well as compatibility with lead bismuth, it is appropriate to lower the incident proton current density and the process temperature, in which temperature range engineering design can control to work, especially in ADS (Accelerator-Driven nuclear transmutation System) concept. The lower limit temperature is determined from the physical melting temperature and the engineering efficiency of the steam generator involved in process control. The material related issues for liquid lead bismuth are mass loss by impinging secondary flow, wettability at the device interface for ultrasonic waves application, detachable control of the slag in the flowing system, stabilized electrical resistance between the material and the liquid lead bismuth interface. Electromagnetic fluid analyses show how flow rate relates electrical resistivity of flow channel material.

Influence of Plastic Deformation on Dissolution Corrosion of Type 316L Austenitic Stainless Steel in Static, Oxygen-Poor Liquid Lead-Bismuth Eutectic at 500°C

CORROSION ◽  
10.5006/2400 ◽  
2017 ◽  
Vol 73 (9) ◽  
pp. 1078-1090 ◽  
Author(s):  
Oksana Klok ◽  
Konstantina Lambrinou ◽  
Serguei Gavrilov ◽  
Erich Stergar ◽  
Tom Van der Donck ◽  
...  
Keyword(s):  
Plastic Deformation ◽  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Liquid Lead ◽  
Type 316L ◽  
316L Austenitic Stainless Steel ◽  
Lead Bismuth Eutectic ◽  
Dissolution Corrosion

Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead

2021 ◽  
Vol 7 (2) ◽  
Author(s):  
Lucia Rozumová ◽  
Lukáš Košek ◽  
Jan Vít ◽  
Anna Hojná ◽  
Patricie Halodová
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Focused Ion Beam ◽  
Ion Beam ◽  
Construction Materials ◽  
Static Condition ◽  
Oxide Thickness ◽  
Liquid Lead ◽  
Flowing Liquid ◽  
Nuclear Systems

Abstract Development of liquid lead cooled nuclear systems requires consideration of compatibility issues with the construction materials. In order to understand the corrosion or passivation behavior of the 316 L austenitic stainless steel, the steel specimens were exposed for 1000 h in liquid lead with 1 × 10−7 wt % oxygen level at 480 °C in static and flowing (velocity 1.6 m/s) conditions. Post-test microscopy investigation using scanning electron microscope with focused ion beam (FIB) was performed and it demonstrated significant differences in the formation of thin oxide layers in the two conditions. Maximum oxide thickness was 2 μm in the static lead (Pb) and less than 0.1 μm in the flowing Pb. In the static condition, oxide scale was not continuous and local corrosion attack was indicated; but in flowing condition the oxide layer was continuous without any corrosion attacks.

scholarly journals Identification of chemical form of stable carbon released from type 304L and 316L stainless-steel powders in alkaline and acidic solutions under low-oxygen conditions

Radiocarbon ◽  
2018 ◽  
Vol 60 (6) ◽  
pp. 1691-1710
Author(s):  
Ryo Nakabayashi ◽  
Tomonari Fujita
Keyword(s):  
Stainless Steel ◽  
Carboxylic Acids ◽  
Safety Assessment ◽  
Silicon Oxide ◽  
Chemical Form ◽  
Low Oxygen ◽  
Colloidal Carbon ◽  
Oxygen Conditions ◽  
Naoh Solution

ABSTRACTThe chemical form of14C released from irradiated stainless steel is a key parameter in the safety assessment of the subsurface disposal system in Japan. In this study, to identify the chemical form of the released carbon, unirradiated stainless-steel powders, which were found to be water-atomized powders with a silicon oxide film, were immersed in NaOH and HCl solutions under low-oxygen conditions for approximately 25 days. The results showed that the main chemical forms of the carbon were colloidal carbon in the NaOH solution and colloidal carbon and formic and acetic acids in the HCl solution. Almost no hydrocarbons were detected in both solution systems. Concerning the source of the colloidal carbon and carboxylic acids, the hypothesis that carbon in the oxide layer is released is considered to be reasonable. The very small amounts of hydrocarbons generated prevented us from discussing the source of the hydrocarbons. To validate the hypothesis and obtain further information on the hydrocarbons, additional experiments are necessary. In particular, for long-term safety assessment, it is important to determine whether the colloidal carbon, carboxylic acids and hydrocarbons are continuously released during the corrosion process. Therefore, information on the temporal evolution of the carbon should be obtained.

Identification of Chemical Form of Carbon Released from SUS304 and SUS316 in Alkaline Solution under Low-oxygen Condition

MRS Advances ◽  
2016 ◽  
Vol 2 (11) ◽  
pp. 597-602 ◽  
Author(s):  
Ryo Nakabayashi ◽  
Tomonari Fujita
Keyword(s):  
Stainless Steel ◽  
Carboxylic Acids ◽  
Iron Hydroxide ◽  
Chemical Form ◽  
Low Oxygen ◽  
Colloidal Iron ◽  
Liquid Samples ◽  
Oxygen Conditions ◽  
Naoh Solution ◽  
Carbon Concentrations

ABSTRACTTo classify the chemical form of stable carbon released from unirradiated stainless steel, which is the material used to simulate irradiated stainless steel, under highly alkaline and low-oxygen conditions, type 304 and 316 stainless-steel powders were immersed in 0.005 M NaOH solution. Gas and liquid samples were analyzed to identify the chemical form of carbon released from the stainless steel. The liquid samples were divided into unfiltered and filtered samples. In the gaseous phase, hydrocarbons such as methane and ethane were not detected. In the liquid phase, carboxylic acids (formic and acetic acids) were detected. However, the sum of the carbon concentrations of the carboxylic acids was significantly lower than the total organic carbon (TOC) concentration in the unfiltered samples. In the filtered samples, the TOC concentration was closer to the sum of the carbon concentrations than that for the unfiltered samples. In addition, the concentrations of the metallic elements (particularly Fe and Cr), which are the main constituents of the stainless steels, tended to decrease upon ultrafiltration. This suggests that the sorption of carbon on metallic compounds (e.g., colloidal iron hydroxide) may have occurred.

Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Oksana Klok ◽  
Konstantina Lambrinou ◽  
Serguei Gavrilov ◽  
Jun Lim ◽  
Iris De Graeve
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Dissolved Oxygen ◽  
Oxygen Concentration ◽  
Steel Specimen ◽  
Liquid Lead ◽  
Lead Bismuth Eutectic ◽  
Dissolution Corrosion ◽  
Steel Heat ◽  
Exposure Conditions

This work focuses on the effect of dissolved oxygen concentration in liquid lead-bismuth eutectic (LBE) on the onset of dissolution corrosion in a solution-annealed 316 L austenitic stainless steel. Specimens made of the same 316 L stainless steel heat were exposed for 1000 h at 450 °C to static liquid LBE with controlled concentrations of dissolved oxygen, i.e., 10−5, 10−6, and 10−7 mass%. The corroded 316 L steel specimens were analyzed by scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS). A complete absence of dissolution corrosion was observed in the steel specimens exposed to liquid LBE with 10−5 and 10−6 mass% oxygen. In the same specimens, isolated “islands” of FeCr-containing oxides were also detected, indicating the localized onset of oxidation corrosion under these exposure conditions. On the other hand, dissolution corrosion with a maximum depth of 59 μm was detected in the steel specimen exposed to liquid LBE with 10−7 mass% oxygen. This suggests that the threshold oxygen concentration associated with the onset of dissolution corrosion in this 316 L steel heat lies between 10−6 and 10−7 mass% oxygen for the specific exposure conditions (i.e., 1000 h, 450 °C, static liquid LBE).

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