Compatibility Of Stainless Steel Research Articles

Isothermal calorimetric observations of the effect of welding on compatibility of stainless steels with high-test hydrogen peroxide propellant

Welding of stainless steels (CRES 316L and CRES 304L) was found to increase surface roughness and more importantly to decrease their compatibility with high-test hydrogen peroxide (HTP). Compatibility was determined by isothermal microcalorimeter (IMC) measurements. Omission of a purge gas enhances welding effects. Previous literature indicated welding causes segregation of chromium and iron in the heat affected zone (HAZ) and in the weld bead itself. It is likely that these surface modifications are responsible for the diminished compatibility, however a direct correlation was not established.

Compatibility of stainless steels and lithium based ceramics with beryllium

Compatibility of stainless steels and lithium based ceramics with beryllium

Compatibility of stainless steels and lithium based ceramics with beryllium

Abstract The introduction of beryllium as a neutron multiplier in ceramic blankets of thermonuclear fusion reactors may give rise to the following compatibility problems: (i) oxidation of Be by ceramics (lithium aluminate and silicates) or by water vapour; (ii) interaction between beryllium and austenitic and martensitic steels. The studies were done in contact tests under vacuum and in tests under wet sweeping helium. The contact tests under vacuum have revealed that the interaction of beryllium with ceramics seems to be low up to 700°C, the interaction of beryllium with steels is significant and is characterized by the formation of a diffusion layer and of a brittle Be-Fe-Ni compound. With type 316 L austenitic steel, this interaction appears quite large at 600°C whereas it is noticeable only at 700°C with martensitic steels. The experiments carried out with sweeping wet helium at 600°C have evidenced a slight oxidation of beryllium due to water vapour which can be enhanced in the front of uncompletely dehydrated ceramics.

Compatibility of stainless steels and lithiated ceramics with beryllium

The introduction of beryllium as a neutron multiplier in ceramic blankets of thermonuclear fusion reactors may give rise to the following compatibility problems: (i) oxidation of Be by ceramics (lithium aluminate and silicates) or by water vapour; (ii) interaction between beryllium and austenitic and martensitic steels. The studies were done in contact tests under vacuum and in tests under wet sweeping helium. The contact tests under vacuum have revealed that the interaction of beryllium with ceramics seems to be low up to 700°C, the interaction of beryllium with steels is significant and is characterized by the formation of a diffusion layer and of a brittle Be-Fe-Ni compound. With type 316 L austenitic steel, this interaction appears quite large at 600°C whereas it is noticeable only at 700°C with martensitic steels. The experiments carried out with sweeping wet helium at 600°C have evidenced a slight oxidation of beryllium due to water vapour which can be enhanced in the front of uncompletely dehydrated ceramics.

Compatibility of stainless steel with Pb-17 At. Pct Li

The corrosion of type 316 stainless steel and Sandvik HT9 by static Pb-17 at. pct Li between 300 and 500 °C was studied. The resulting weight losses were significantly greater than those of these steels in lithium. The corrosive attack was very uniform, and the roomtemperature tensile properties of the steels were unaffected by the exposure. The application of molten Pb-17 at. pct Li as a tritium-breeding fluid in conjunction with ferrous alloys in a fusion reactor may be limited to 400 °C or below.

The compatibility of stainless steels with low-sulphur UCS fuels

Sodium-bonded and vacuum-bonded compatibility tests at 600 and 700°C between stainless steels and UCS fuels of differing sulphur contents and stoichiometries revealed that, over the range of compositions studied, the amount of carburisation of the cladding is a linear function of only the total non-metal content (C + O + N + S) of the fuel, and does not depend on the actual sulphur content of the fuel. A UC and a UCS fuel with the same non-metal content therefore cause equal amounts of carburisation of the cladding. X-ray and microstructural investigations of the fuels further showed that a single-phase region does not exist at non-metal contents greater than 50 at%, and that sulphur probably behaves as a carbon equivalent in that it enters the UC lattice in solid solution, but displaces a carbon atom which is freed to form a higher carbide. The conclusion is therefore drawn that the addition of sulphur to UC fuels has no direct advantage at non-metal contents greater than 50 at% as far as the compatibility behaviour of the fuel towards the cladding is concerned.

The nature of the oxide film formed on stainless steel immersed in concentrated hydrogen peroxide (H.T.P.)

AbstractWhen stainless steel is immersed in H.T.P. an oxide film is formed on the surface of the metal. The rate of formation, composition and stability of this film have been investigated by chemical analysis and electrometric methods. The film consists mainly of oxides of iron and at 30° it grows to a fairly constant thickness of 3×10−6 cm. in 3–4 weeks. The compatibility of stainless steel with H.T.P. is explained in terms of the solubility and catalytic activity of the main constituents of stainless steel.