Abstract: A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor. The cooling system has cooling assemblies that are housed in protective structures, which shield the cooling assemblies from projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to passively cool the cooling assemblies.

Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator.

Abstract: An example system for programmatically extracting data from a big data source includes: a processor; and system memory encoding instructions which, when executed by the processor, cause the system to: extract metadata from the big data source using the utility; transform the metadata into a standard format; and load the metadata in a repository.

Abstract: The repositioning station (200) allows a continuous shingled stream (120) of overlapping semirigid planar articles (100) to be transported on an incoming conveyor (122) along a transport circuit (204) onto an outgoing conveyor (302) so as to form a stack that can be carried away upon the outgoing conveyor (302). The repositioning station (200) includes a lateral deviation assembly (210) and may also include a final positioning assembly (212). The transport circuit (204) within the lateral deviation assembly (210) follows a generally ellipsoidal deviation path to veer the shingled stream (120) and also to pivot the articles (100) therein about a curvilinear axis (206) from a facedown position to an upright position. The outgoing conveyor (302) can carry the cartons (100) in a direction that is parallel to that of the incoming conveyor (122).

Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator.

Abstract: A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor and the structure of the cooling system prevents gas that is not in the closed circuit to approach the reactor within neutron radiation distance. The cooling systems has cooling assemblies that are housed in protective structures, which shield the cooling assemblies for projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to cool the cooling assemblies.

Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator.

Abstract: Techniques related to data collaboration between different entities are disclosed. In an embodiment, a graph may be displayed in a computer graphical user interface. The graph may include nodes and edges. Each node may represent a distinct data object. Each edge may represent one or more relationships between the two distinct data objects. Based on one or more redaction criteria, a portion of the graph may be identified to be redacted before the graph is exported. Display of the graph in the computer graphical user interface may be updated to remove display of the portion of the graph. After the updating, a request to export the graph may be received. Responsive to receiving the request, a machine-readable representation of a redacted graph may be exported.

Abstract: Techniques related to data collaboration between different entities are disclosed. In an embodiment, a graph may be displayed in a computer graphical user interface. The graph may include nodes and edges. Each node may represent a distinct data object. Each edge may represent one or more relationships between the two distinct data objects. Based on one or more redaction criteria, a portion of the graph may be identified to be redacted before the graph is exported. Display of the graph in the computer graphical user interface may be updated to remove display of the portion of the graph. After the updating, a request to export the graph may be received. Responsive to receiving the request, a machine-readable representation of a redacted graph may be exported.

Abstract: An example system for programmatically extracting data from a big data source includes: a processor; and system memory encoding instructions which, when executed by the processor, cause the system to: extract metadata from the big data source using the utility; transform the metadata into a standard format; and load the metadata in a repository.

Abstract: A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor and the structure of the cooling system prevents gas that is not in the closed circuit to approach the reactor within neutron radiation distance. The cooling systems has cooling assemblies that are housed in protective structures, which shield the cooling assemblies for projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to cool the cooling assemblies.

Abstract: A molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.

Abstract: A pneumatic motor assembly that includes a pneumatic motor, which is driven by a compressed gas. The pneumatic motor assembly has a magnet assembly that magnetically couples the pneumatic motor assembly to an implement. After having being used to drive a pneumatic motor, the gas, which has expanded and become colder, cools the magnet assembly The pneumatic motor assembly can thus enable the use to the implement at temperatures at which the magnet assembly would otherwise reach or exceed the maximum operating temperature of the magnet assembly. A flow induction system that includes the pneumatic motor assembly. A method of operating a pneumatic motor assembly that also cools a magnet assembly that is part of the pneumatic motor assembly.

Abstract: A system with methodology for providing multi-language support for dynamic ontology. In one embodiment, for example, a method comprises: storing an ontology for a data store, wherein the ontology comprises a plurality of data types; for each data type of the plurality of data types: storing, in the ontology, one or more display values, wherein each display value is associated with a locale; determining a locale identifier corresponding to a particular locale; selecting a particular display value corresponding to the particular locale; displaying the particular display value.

Abstract: A system with methodology for providing multi-language support for dynamic ontology. In one embodiment, for example, a method comprises: storing an ontology for a data store, wherein the ontology comprises a plurality of data types; for each data type of the plurality of data types: storing, in the ontology, one or more display values, wherein each display value is associated with a locale; determining a locale identifier corresponding to a particular locale; selecting a particular display value corresponding to the particular locale; displaying the particular display value.

Abstract: A system with methodology for providing multi-language support for dynamic ontology. In one embodiment, for example, a method comprises: storing an ontology for a data store, wherein the ontology comprises a plurality of data types; for each data type of the plurality of data types: storing, in the ontology, one or more display values, wherein each display value is associated with a locale; determining a locale identifier corresponding to a particular locale; selecting a particular display value corresponding to the particular locale; displaying the particular display value.

Abstract: Techniques related to data collaboration between different entities are disclosed. In an embodiment, a graph may be displayed in a computer graphical user interface. The graph may include nodes and edges. Each node may represent a distinct data object. Each edge may represent one or more relationships between the two distinct data objects. Based on one or more redaction criteria, a portion of the graph may be identified to be redacted before the graph is exported. Display of the graph in the computer graphical user interface may be updated to remove display of the portion of the graph. After the updating, a request to export the graph may be received. Responsive to receiving the request, a machine-readable representation of a redacted graph may be exported.

Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator.

Abstract: A cooling system to remove decay heat removal from a nuclear core of a nuclear reactor when the nuclear reactor cesses to operate due to unforeseen conditions such as, for example, loss of electrical power to pumps circulating the primary coolant in the nuclear reactor. The cooling has a conduit structure that defines a sealed closed circuit through which a cooling fluid circulates through natural convection. In some embodiments, the cooling system of the present disclosure is always functioning. That is, the cooling system continuously extracts heat from the nuclear core. In these embodiments, the cooling system does not need to be actuated in any way when the nuclear reactor shuts down unexpectedly. In other embodiments, the cooling system can be turned on automatically upon loss of electrical power.

Abstract: A molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.