摘要:
Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibt a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.
摘要:
Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.
摘要:
Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about .31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.
摘要:
A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.
摘要:
Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about 0.31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.
摘要:
A harness vest carries a lighting system for safety and utility. The vest includes holsters for light modules on front and back shoulder pads. The light modules may be removable or fixed LED strips attached to the front and back shoulder pads. Each lighting module is removable and is controlled by on/off buttons and front-mounted control panels for separate use as portable, personal, lighting devices. Modules are magnetic and may be removable from the harness best and attached to other surfaces for illuminating a work area. The user controls brightness, mode (such as strobe, strobe frequency), and color. The vest can be added to a reflector cover as part of a 5-point breakaway reflector vest.
摘要:
The present invention allows for a robust design using manufacturability models. A method, system and/or computer usable medium may be provided in an integrated circuit design to track sensitivity to a variation of process from wafer to wafer and/or fab to fab in order to assist the designers to anticipate the variations to improve the final yield of the products.
摘要:
Disclosed are a method, system, and computer program product for providing customizable information in designing electronic circuits with electrical awareness. The method or the system displays a portion of a physical design of an electronic circuit in a first display area. The method or the system receives or identifies a user's or a system's manipulation of the portion of the physical design of the electronic circuit. The method or the system then determines and displays an in situ response to the manipulation in the first display area. The method or the system may further display, in the first display area or in another display area, result(s) relating to the physical data of a component, electrical parasitic(s) associated with the physical data, electrical characteristic(s) associated with the physical data or the electrical characteristic(s), or other element(s) of the physical design that is impacted by the manipulation.
摘要:
A data modeling method for modeling data for an electronic program guide (EPG) at a broadcast headend is described. The method includes grouping receiver types according to a first set of characteristics associated with a receiver type, thereby producing a plurality of groups of receivers, assigning a bit-number to each group of receivers, providing EPG data, the EPG data including data for display at an EPG, the EPG data being included in a data fragment, evaluating the data fragment and the EPG data included therein according to at least one characteristic from a second set of characteristics, thereby producing a result, adding metadata to the data fragment, the metadata including a bit field including the assigned bit number, the bit number being determined in accordance with the result, the metadata being indicative of at least one characteristic from the first set of characteristics with which a data container and EPG data included therein are associated, and broadcasting the data fragment in the data container. Related methods and apparatus are also described.