Sintered Nickel Casing for Irradiation Targets

2016 ◽  
Vol 869 ◽  
pp. 484-489
Author(s):  
R.S.L. Miyano ◽  
H. Takiishi ◽  
E.P. Soares ◽  
A.M. Saliba-Silva ◽  
J.L. Rossi
Keyword(s):  
Stainless Steel ◽  
High Purity ◽  
Nickel Powder ◽  
Nuclear Reactor ◽  
Mercury Porosimetry ◽  
Boundary Surface ◽  
Hydraulic Press ◽  
Titanium Machining ◽  
Powder Samples ◽  
Metallic Cylinder

The aim of this work was to develop an alternative way to obtain casings used with irradiation targets containing uranium, for the production of the radionuclide Mo-99-Tc99m. The targets used for the production of Mo-99 are materials containing U-235 designed to be irradiated in a nuclear reactor. Usually these targets are encapsulated in aluminum or stainless steel. The idea here is to obtain casings by encapsulating a uranium button or a metallic cylinder with compacted and sintered nickel powder, this serving as a sealing for the fissile products occurring during U-235 irradiation. The sintered high purity nickel powder samples were compacted in uniaxial hydraulic press at 195 MPa. The sintering of the samples was carried out in an open-air furnace in an atmosphere with a certain control using titanium-machining chips at 600 °C. The samples bulk density was evaluated by the Archimedes' principle. The porosity of 20.08% was measured by mercury porosimetry. The microstructure was investigated by scanning microscopy revealing interconnected porosity and nickel oxide at the particles boundary surface. The results obtained by sintering of nickel powder according to the experimental undertaken, indicate the feasibility of achieving a casing for uranium targets.

SANDVIK BIOLINE HIGH-N

Alloy Digest ◽  
2000 ◽  
Vol 49 (6) ◽  
Keyword(s):  
Stainless Steel ◽  
Corrosion Resistance ◽  
Physical Properties ◽  
Tensile Properties ◽  
Surface Finish ◽  
High Purity

Abstract Sandvik Bioline High N is a molybdenum-alloyed stainless steel for implant applications. Corrosion resistance to physiological environments is good. The alloy is of high purity and has an excellent surface finish. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on corrosion resistance. Filing Code: SS-793. Producer or source: Sandvik.

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.

Corrosion Behavior of High Purity Vanadium

CORROSION ◽  
1960 ◽  
Vol 16 (2) ◽  
pp. 70t-72t ◽  
Author(s):  
DAVID SCHLAIN ◽  
CHARLES B. KENAHAN ◽  
WALTER L. ACHERMAN
Keyword(s):  
Stainless Steel ◽  
Nitric Acid ◽  
Corrosion Behavior ◽  
High Purity ◽  
Galvanic Corrosion ◽  
Acid Solutions ◽  
Ocean Water ◽  
Nitric Acid Solutions

Abstract Chemical and galvanic corrosion experiments at 35 C show that ductile vanadium is resistant to corrosion in substitute ocean water. It is also resistant in 60 percent sulfuric and 20 percent hydrochloric acids but corrodes rapidly in nitric acid solutions. Vanadium is less noble than stainless steel and copper and more noble than aluminum, magnesium and steel (SAE 4130) in substitute ocean water. 6.3.18

Aluminization of high purity iron and stainless steel by powder liquid coating

2004 ◽  
Vol 52 (8) ◽  
pp. 2173-2184 ◽  
Author(s):  
Koji Murakami ◽  
Norihide Nishida ◽  
Kozo Osamura ◽  
Yo Tomota ◽  
Tetsuya Suzuki
Keyword(s):  
Stainless Steel ◽  
High Purity ◽  
Purity Iron ◽  
High Purity Iron

scholarly journals Development of an assembly for the realization of a transducer able to operate at very high temperatures

2019 ◽  
Vol 283 ◽  
pp. 07011
Author(s):  
Didier Flotté ◽  
David Macel ◽  
Abd Ennour Bouzenad ◽  
Frédéric Navacchia
Keyword(s):  
Stainless Steel ◽  
High Temperatures ◽  
Nuclear Reactor ◽  
New Technology ◽  
Operating Conditions ◽  
Equivalent Diameter ◽  
Assembly Technique ◽  
The One ◽  
Piezoelectric Disc ◽  
Very High

Monitoring the operation of the latest-generation nuclear reactor requires ultrasonic transducers able to operate at very high temperatures (> 600°C). To achieve this, CEA has requested from “Institut de Soudure” to help developing a new technology for these transducers compared to the one previously developed. This began with the development of a reliable assembly technique between a lithium niobate piezoelectric disc whose Curie temperature exceeds 1100°C and stainless steel discs. The chosen solution was to braze the niobate disc between two stainless steel discs. Parallel to this development, it was also necessary to develop a NDE procedure to verify the quality of the brazing assemblies. This development began with a simulation of immersion ultrasonic testing of the assemblies. The constraints were to be able to control the two brazed interfaces from the same access face, with the possibility of detecting and dimensioning defects with an equivalent diameter of 0.25 mm. This phase is important to define the optimal transducer with the associated operating conditions. The first assemblies validated the preliminary choices. To exploit the cartographies obtained, a signal processing procedure was developed. This enabled an automatic characterization of the indications observed. However, the analysis of the signals observed proved to be more complex than the one predicted by the simulation. Once the origin of the various observed signals was identified it was then possible to define windows allowing the construction of the cartographies to analyze. In case of a good quality assembly, it was possible to qualify the generated beam and to image it in the focal plane but with an observed signal having a very low damping. These first encouraging results, however, show that there is still some validation and development work to increase the sensitivity of the developed translator and its damping.

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