Abstract: A dilution apparatus for diluting a gas sample. The apparatus includes a sample gas conduit having a sample gas inlet end and a diluted sample gas outlet end, and a sample gas flow restricting orifice disposed proximate the sample gas inlet end connected with the sample gas conduit and providing fluid communication between the exterior and the interior of the sample gas conduit. A diluted sample gas conduit is provided within the sample gas conduit having a mixing end with a mixing space inlet opening disposed proximate the sample gas inlet end, thereby forming an annular space between the sample gas conduit and the diluted sample gas conduit. The mixing end of the diluted sample gas conduit is disposed at a distance from the sample gas flow restricting orifice. A dilution gas source connected with the sample gas inlet end of the sample gas conduit is provided for introducing a dilution gas into the annular space, and a filter is provided for filtering the sample gas.

Abstract: The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to allow a user to selectively populate a loading map with fuel bundles residing in at least one fuel pool.

Abstract: The method of improving nuclear reactor performance involves generating an operational solution for a nuclear reactor based on a constraint accounting for a problem with operation of the nuclear reactor. The generated operational solution can then be implemented at the nuclear reactor.

Abstract: There is disclosed a millimeter wave power source module which may include a plurality of submodules. Each submodule may include a further plurality of circuit devices. Each circuit device may have an input coupled to a corresponding receiving element and an output coupled to a corresponding radiating element. Each submodule may also include a heat spreader for removing heat from the plurality of circuit devices. A combination RF feed network and heat sink may include a waveguide horn to couple an RF input wave to the receiving elements on each of the plurality of submodules. The combination RF feed network and heat sink may also include a heat exchanger thermally coupled to the heat spreaders of each of the plurality of submodules.

Abstract: Methods for evaluating robustness of solutions to constraint problems include: (a) determining one or more inputs for the constraint problem; (b) determining bias, uncertainty, or bias and uncertainty of the one or more inputs; (c) randomly perturbating at least one of the one or more inputs based on the bias, uncertainty, or bias and uncertainty of the one or more inputs to determine one or more modified inputs; (d) generating a solution to the constraint problem based on the one or more modified inputs; (e) storing the solution; (f) repeating (c) through (e) until multiple solutions are stored; and/or (g) determining the robustness of the stored multiple solutions by comparison of the stored multiple solutions to each other. The one or more modified inputs include the randomly perturbated input or inputs and/or the non-perturbated input or inputs.

Abstract: Control rod guide tubes for a nuclear reactor having a body with an axial length that defines a lower end portion and an upper end portion and a cavity within a substantial length of the body. Orifices are included at the upper and lower end portions of the body. A control rod chamber is located within the cavity and is configured for receiving a control rod. A plurality of ports is coupled to the cavity and is positioned at a substantial length from the upper end portion of the body. Also included are at least two flow channels within the cavity that extend a substantial portion of the axial length of the body. Each flow channel is fluidly coupled to one or more of the ports for receiving fluid flow from outside the body and an outlet proximate to the upper end portion of the body for providing the received fluid flow.

Abstract: Example embodiments and methods may provide segmented waste rods capable of containing and disposing of waste generated from spent nuclear fuel, including elements left over from fuel that has been harvested for desired isotopes produced in the fuel. Example methods may provide methods for forming and using example embodiment segmented waste rods.

Abstract: This invention is generally related to therapeutic treatment of a coronary vessel wall, and more particularly, to systems and methods for improving uptake of therapeutic agents within the endothelium for enhanced delivery of therapeutic agents to a treatment site. A medical device is provided that is capable of reducing the pressure applied to a vessel wall and delivering a therapeutic agent into the vessel wall. Also, methods are described for using the device to facilitate delivery and uptake of a therapeutic agent into the vessel wall.

Abstract: The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to allow a user to selectively populate a loading map with fuel bundles residing in at least one fuel pool.

Abstract: An apparatus and method for diluting and cooling that is extracted from high temperature and/or high pressure industrial processes. Through a feedback process, a specialized, CFD-modeled dilution cooler is employed along with real-time estimations of the point at which condensation will occur within the dilution cooler to define a level of dilution and diluted gas temperature that results in a gas that can be conveyed to standard gas analyzers that contains no condensed hydrocarbon compounds or condensed moisture.

Abstract: A fuel support for a nuclear reactor may include: a plurality of fuel support apertures, each fuel support aperture dimensioned for receiving a lower tie plate of a fuel assembly; and a plurality of lumens, each lumen being coupled to a different fuel support aperture. At least one lumen may be configured for attenuating a fluid flow differently than the fluid flow in at least one other of the lumen.

Abstract: Example embodiments and methods are directed to irradiation target retention devices that may be inserted into conventional nuclear fuel rods and assemblies. Example embodiment devices may hold several irradiation targets for irradiation during operation of a nuclear core containing the assemblies and fuel rods having example embodiment irradiation target retention devices. Irradiation targets may substantially convert to useful radioisotopes upon exposure to neutron flux in the operating nuclear core and be removed and harvested from fuel rods after operation.

Abstract: In various embodiments, the system comprises a system for storing radioactive material, wherein the system includes a storage pool for storing a plurality of radioactive objects submersed in a radiation shielding and cooling liquid. The system additionally includes an assembly building located above the storage pool for constructing one or more radioactive articles using the radioactive objects transferred from the storage pool. Furthermore, the system includes at least one transfer shaft connecting the storage pool and the assembly building. The transfer shaft(s) are used for transferring the radioactive objects directly from within the storage pool to an interior of the assembly building and directly from the interior of the assembly building into the storage pool.

Abstract: A guide catheter and a needle catheter are disclosed. The guide catheter construction provides for maximum articulation of the deflectable tip and maximum torque response during rotation. The needle catheter may include a release mechanism that imparts a sudden force to the needle in order to facilitate tissue penetration.

Abstract: A tendon deflection system including a shaft, a plurality of tendons movably disposed within the shaft, and a force-balancing element coupled to the tendons. In a first section, the plurality of tendons are arranged around the shaft at equal angles to each other and at an equal distance from the center of the shaft. The tendons operating in concert with the force-balancing element minimize the moment expressed in the first section. The second section is deflectable and includes at least one tendon, extending from the plurality of tendons in the first section, which is arranged along one side of the shaft such that the bending moment expressed in the second section is greater than the first section.

Abstract: A tendon deflection system including a shaft, a plurality of tendons movably disposed within the shaft, and a force-balancing element coupled to the tendons. In a first section, the plurality of tendons are arranged around the shaft at equal angles to each other and at an equal distance from the center of the shaft. The tendons operating in concert with the force-balancing element minimize the moment expressed in the first section. The second section is deflectable and includes at least one tendon, extending from the plurality of tendons in the first section, which is arranged along one side of the shaft such that the bending moment expressed in the second section is greater than the first section.

Abstract: Example embodiments are directed to apparatuses and methods for producing radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable from nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes.

Abstract: Fuel supports for a nuclear reactor and methods of modifying fluid flow in a reactor using a fuel support. The fuel supports include a plurality of lumens and a plurality of fuel support apertures with each fuel support aperture being dimensioned for receiving a lower tie plate of a fuel assembly. Each lumen is fluidly coupled to a different fuel support aperture. At least one lumen is configured for attenuating a fluid flow differently than the fluid flow in at least one other of the lumen.

Abstract: Disclosed are various embodiments of methods and systems related to double-pendulum crane control. In one embodiment for determining a specified insensitivity (SI) input shaper for a double-pendulum crane, the method using a processor system to implement the steps including determining a plurality of insensitivity ranges based upon operational parameters associated with the double-pendulum crane; and determining SI input shaper parameters based upon tolerances corresponding to the plurality of insensitivity ranges, the SI input shaper parameters including an amplitude and a time corresponding to each impulse of the SI input shaper.

Abstract: A guide catheter and a needle catheter are disclosed. The guide catheter construction provides for maximum articulation of the deflectable tip and maximum torque response during rotation. The needle catheter may include a release mechanism that imparts a sudden force to the needle in order to facilitate tissue penetration.