Abstract: A computer method and system provides for graphical specification of inquiries and includes a corresponding progressive summary. The inquiries operate on stream data. Users graphically specify an inquiry in a graphical user interface according to an ontology. The invention system generates a plain-text translation of the graphical description of the inquiry and displays the generated plain-text description in a progressive summary in the graphical user interface. The system continually updates and generates the display of the plain-text description during user construction of the inquiry. This provides feedback to the user for improved construction of the inquiry.

Abstract: Presented is a computer system and user interface for seamlessly integrating the creation and submission of persistent queries, and for collecting and presenting the real-time results of those queries, into the context of one's work and directly structured work artifacts. Users are provided a real-time awareness of what is happening to their persistent queries and their results, from within the work context of the artifact and program application used during creation and submission of the queries. Rather than having to visit a separate alerting application, the user is able to manage queries and query results directly from a subject application, such as a problem-solving application.

Abstract: Computer method and apparatus represent users by respective avatars in a subject virtual environment. The invention system displays the avatars in the virtual environment, and for each avatar, displays in proximity to the avatar, a respective trail of virtual contact objects. The respective trail of virtual contact objects is associated with the user represented by the avatar and serves as a visual indication of presence and activeness (level of activity) of the user in the subject virtual environment. Each virtual contact object in the respective trail stores and provides user contact data of the user and is persistable upon end-user command.

Abstract: A computer method and system familiarizes users in a group in shared synchronous environments. As part of operation of a given shared synchronous online environment, the invention generates an icebreaking activity for a group of users. The generated ice breaking activity has content from at least one data source external to the given online environment. The content may be mined user profiles, images and other user information from other data sources that users provide information to. The invention allows free form conversation among the group of users during participation in the generated ice-breaking activity. Such participation by the users in the generated ice-breaking activity and free form conversation among the users enable users to become familiar with each other's human persona.

Abstract: A computer system and method providing on-demand extension of ontology in an ontology use process. A support module responds to a creation event in the ontology use process. The support module defines ontology specification for a newly created item, in the creation event, in a manner substantially free of disruption or interruption to the ontology use process. An ontology manager incorporates the defined ontology specification into the ontology during the ontology use process such than an on-demand extension of the ontology results.

Abstract: Under the present invention, an executable object such as binary or JAVA byte code corresponding to the software application is obtained. Based on an analysis of the software application, points for introducing the collaborative components are identified. A set of executable code (e.g., an Aspect) to introduce the collaborative components at the identified points is then defined and built. Thereafter, the set of executable code and the collaborative components are linked to the executable object.

Abstract: The present invention automatically links web documents to other, existing web documents. Specifically, when a web document is requested, the content therein will be compared to an index of references and addresses to determine whether any related web documents exist. If any of the content matches any of the references in the index, a related web document does exist. The address corresponding to the related web document will then be bound to the matching content of the requested web document. This process occurs before the web document is displayed to the user and alleviates the problems associated with hyperlinks to non-existing web documents.

Abstract: A method and system are provided for visualization of information stored in database records. Data visualizations offer a view of the underlying database records and are created and stored with in the database along with the database records. A data visualization includes data visualization points that are associated with underlying database records. Each data visualization point provides a direct drill-down capability, allowing for the full record display of the underlying database record associated with the a visualization point. Specific user interface mechanisms are provided with the data visualizations to allow a user to navigate among the database records as well as to manipulate the data stored in the underlying database records. Data manipulation may occur as a result of direct user interaction with the visualization points or through a specific user interface designed to allow data modification.

Abstract: The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly.

Abstract: An improved fuel rod is provided having a part-length fuel rod portion that improves performance with respect to typical part-length fuel rods without significant degradation of the benefits that are achieved by using such a system, e.g., improved fuel utilization, stability, and shut down margin. The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein.

Abstract: An improved fuel rod is provided having a part-length fuel rod portion that improves performance with respect to typical part-length fuel rods without significant degradation of the benefits that are achieved by using such a system, e.g., improved fuel utilization, stability, and shut down margin. The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein.

Abstract: An improved fuel rod is provided having a part-length fuel rod portion that improves performance with respect to typical part-length fuel rods without significant degradation of the benefits that are achieved by using such a system, e.g., improved fuel utilization, stability, and shut down margin. The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein.

Abstract: A low pressure drop spacer for positioning and retaining the fuel rods of a nuclear fuel assembly in which a plurality of upper and lower spring forks which extend through apertures in the side wall of the spacer into the assembly and through apertures in grid members which divide the assembly. The intersection and superposition of the spring forks, side wall and grid members form fuel rod passageways through which the fuel rods extend.

Abstract: A boiling water reactor fuel rod assembly is provided having a plurality of fuel rod spacers which are slidably receivable within an outer channel. Each of the rod spacers is formed of at least one lattice which defines a plurality of fuel rod retaining cells. The lattice is constructed of a plurality of pairs of oppositely facing springy support strips, with each support strip having a plurality of spring-loaded indentations. In an unloaded condition, oppositely facing indentations of each pair of strips, which define each cell, are displaced closer to one another. In a loaded condition, the oppositely facing cell indentations are forced away from each other by the fuel rods so that the springloaded indentations support and retain the fuel rods.

Abstract: A fuel assembly for a boiling water nuclear reactor is provided comprising an elongated central water channel including wall members that define an enclosed fluid flow path therethrough, the channel includes a lower opening for receiving water and allowing water to flow through the fluid flow path and at least one outlet opening. At least one partial water rod is provided that is coupled to a partial fuel rod so as to be disposed axially above the partial fuel rod. The partial water rod includes an inlet opening in fluid communication with the outlet opening of the central water channel so as to allow water to flow from the water channel into an interior of the partial water rod.

Abstract: A grid spacer for a nuclear reactor fuel assembly is formed of two superposed combs. Each comb has a base strip which extends the width of the assembly. To it are attached parallel grid strips which are free at their other ends. The grid strips are perpendicular to the base strip and are formed for spring engagement with the fuel rods of the assembly. The combs can be inserted from the sides of the assembly, so that an additional or substitute spacer can be added to the assembly without disassembling the latter.

Abstract: A debris screen for a fuel assembly for a reactor to which coolant fluid is supplied comprises a substantially planar plate member having an array of coollant openings extending through the plate member dimensioned to trap at least a portion of debris particles carried by the coolant; and a skirt member enclosing the periphery of the plate member; each of the coolant flow openings having a coolant entry region at a lower surface, a coolant exit region at an upper surface and a coolant flow path extending between the entry and exit regions, the flow path including an intermediate segment laterally offset from the entry and exit regions to cause coolant to change direction of flow in the intermediate segment and thereby prevent at least a portion of the debris particles from passing through the plate members.

Abstract: A spring member is formed of at least two layers metallurgically bonded together uniformly and having significantly different rates of irradiation growth, so that the differential growth of the layers results in increased stress in a predetermined direction. The layers may be of different metals or of similar metals which have been treated to give them different growth rates, such as zircaloy with different tin and oxygen content. Examples of other properties which may be used to obtain differential growth rates for the two layers when they are of material with substantially the same constituents are alpha-beta phase transformation temperature, the annealing temperature, the work history, partial recrystallization, and precipitation hardening.

Abstract: An intermediate mixing grid for nuclear reactor fuel assemblies is made without the usual perimeter strip. The ends of the grid members are formed so that they hold the fuel rods at the edges of the assembly in place.

Abstract: A fuel assembly for nuclear reactors which comprises the usual upper and lower tie plates and fuel rods extending between them is made debris-resistant by providing a grid spacer in contact, or very nearly so, with the lower tie plate and so positioned as to subdivide the usual openings in the lower tie plate which are provided for the passage of cooling water. This causes debris to be trapped in the openings of the lower tie plate, and keeps it from contacting the fueled portion of the assembly.