摘要:
A method for mitigating crack initiation and propagation on the surface of metal components in a water-cooled nuclear reactor. An electrically insulating coating doped with a noble metal is applied on the surfaces of IGSCC-susceptible reactor components. The preferred electrically insulating material is yttria-stabilized zirconia doped with palladium or platinum. The presence of an electrically insulating coating on the surface of the metal components shifts the corrosion potential in the negative direction without the addition of hydrogen. Corrosion potentials .ltoreq.-0.5 V.sub.SHE are believed to be achievable even at high oxidant concentrations and in the absence of hydrogen, although the coatings are believed to be particularly suited to applications where a reductant, such as hydrogen, is present.
摘要:
Irradiation assisted stress corrosion cracking occurring in the metallic core components of light water nuclear reactors is reduced by the use of austenitic stainless steel alloys containing a maximum of about 0.03% nitrogen, as well as about 0.025% to about 0.067% carbon, about 1.5% to about 2.0% manganese, a maximum of about 0.005% phosphorus, a maximum of about 0.05% silicon, and a maximum of about 0.005% sulfur.
摘要:
Machine parts are disclosed which are subjected to rolling or sliding conditions, wherein the friction partners are protected by layers with low static and dynamic coefficients of friction which are selected with regard to their tribological properties and whereby the layers are constituted by carbides and/or nitrides and/or carbonitrides and/or borides and/or silicides and/or oxides of an element or elements selected from Groups III to VIII of the Periodic Table in the form of mixtures or mixed crystals which are deposited in a suitable manner and, according to their physiochemical properties, are combined for the particular application. Preferably one of the friction partners comprises TiC or MoSi.sub.2 and the other comproses TiN or SiC or Si.sub.3 N.sub.4.
摘要:
The invention described herein is intended for use primarily as a nuclear containment structure. Such structures are required to surround the nuclear steam supply system and to contain the effects of breaks in the nuclear steam supply system, or i.e. loss of coolant accidents. Nuclear containment structures are required to withstand internal pressure and temperatures which result from loss of coolant accidents, and to provide for radiation shielding during operation and during the loss of coolant accident, as well as to resist all other applied loads, such as earthquakes. The nuclear containment structure described herein is a composite nuclear containment structure, and is one which structurally combines two previous systems; namely, a steel vessel, and a lined concrete structure.Whereas the steel vessel provides strength to resist internal pressure and accommodate temperature increases, the lined concrete structure provides resistance to internal pressure by having a liner which will prevent leakage, and which is in contact with the concrete structure which provides the strength to resist the pressure.
摘要:
A hot or cold operating cast pressure container having an inner steel lining which positively or nearly positively engages the inner wall of the cast pressure container directly or indirectly through the intervention of a filling compound having thermal insulation. The cast pressure container also has a framework for stabilizing the lining against undue deformations. This framework is connected with the cast structure by anchoring elements. Spacers are provided between the framework and the lining.
摘要:
A pressure vessel, containment or burst shield for a nuclear reactor has a substantially circular cover (closing the top or bottom of a cylindrical casing or shell) comprised of a plurality of layers, each formed from a multiplicity of segments meeting a central part. The adjoining segments of each layer meet at joints which are staggered with respect to the joints of the adjacent layers above or below and hence no continuous crevices are provided through the cover. Tension members extend through aligned passages of the several layers and provide support against shear and thrust forces.