Westinghouse Electric Company LLC

Westinghouse Electric Corporation

David L Stucker

Robert J Fetterman

Jeffrey L Bradfute

Michael D Heibel

Radu O Pomirleanu

Yu Chung Lee

Michael J Hone

Levie David Smith, Iii

Joseph C Long

Michael C Misvel

Yonghwan Kim

William T Bogard

C Joseph Long

Hugh J Murphy, Jr

Larry E Erin

Radu O Pomirleaunu

An apparatus and method are described which enable real time measurements to measure the margin to criticality in a process for manufacturing fissile materials. An exemplary apparatus includes a neutron source capable of being modulated, an optional moderator to reduce the thermal energy of neutrons from the neutron source, a collimator for controlling the direction of any neutrons emanating in use from the target, a plurality of detector arrays positioned in predetermined locations relative to a process vessel for detecting process variables and for sending signals representative of the process variables in real time to a processor for receiving the signals and converting the detected process variables into margin to criticality measurements.

Method and apparatus for real-time measurement of fissile content within chemical and material handling processes

The invention relates to UFtransport and process containers to store UFenriched up to 20 percent by weightU in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF. The containers may be produced by additive manufacturing methods.

UFtransport and process container (30W) for enrichments up to 20% by weight

A detection apparatus is usable to detect the neutron absorption capability of a control element of a nuclear installation and includes a neutron radiograph apparatus and a robot apparatus. The neutron radiograph apparatus includes a neutron emission source of variable strength, a detector array, a mask apparatus and a positioning robot all under the control of a central processor and data acquisition unit. The neutron emission source is advantageously switchable between an ON state and OFF state with variable source strength in the ON state, which avoids any need for shielding beyond placing the neutron emission source in an inspection pool at the nuclear plant site including but not limited to the spent fuel or shipping cask laydown pools. The neutron emission source is situated at one side of a wing of the control element and generates a neutron stream, the detector array is situated on an opposite side of a wing, and the neutron emission source and detector array are robotically advanced along the wing. The detector array is monitored in real time, and various masks of the mask apparatus can be positioned between the neutron emission source and the detector array to more specifically identify the position on the blade where the neutrons are passing through.

Detection apparatus and method of detecting the neutron absorption capability of a control element of a nuclear installation

An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. The advanced initial core fuel configuration includes a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed.

Advanced first core fuel assembly configuration

An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. A method of implementing such an initial core involves providing a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed.

Advanced first core fuel assembly configuration and method of implementing the same

A neutron emitting assembly, which is useful in nuclear reactors and other industrial applications, is made of a major amount of beryllium encapsulating a minor amount ofCf, which can be placed in a capsule having end plugs and a holding spring.

Primary neutron source multiplier assembly

A control rod having a lower tip absorber material which exhibits substantially lower irradiation induced swelling than a second absorber material which extends above the lower tip absorber material. The lower tip absorber material having a substantially lower reactivity worth than the second absorber material, extends from a lower end plug of the control rod to an elevation just above a dashpot in a thimble guide tube in a nuclear fuel assembly when the control rod is fully inserted within the thimble guide tube.

Nuclear reactor robust gray control rod

An improved grid for use in a fuel assembly of a nuclear reactor includes a plurality of straps connected in a lattice, with a plurality of mixing vanes being disposed on the straps and being arranged such that the hydraulic forces on the mixing vanes generally cancel one another out. The mixing vanes of diagonal quadrants of the grid are generally aligned with diagonally disposed imaginary alignment planes. Each strap includes a plurality of strap members, with each strap member including a spring and a pair of dimples. The spring includes a contoured spring embossment having a greater radius of curvature in a relaxed condition than the radius of a fuel rod. Each dimple includes a similarly configured contoured dimple embossment. The spring embossment is mounted on a pair of legs that extend nonlinearly between a first plate and a second plate of each strap member to increase compliance thereof.

Nuclear reactor with improved grid

A safety grade protection system for monitoring parameters indicative of the status of a core of a nuclear reactor, and reducing the criticality of the nuclear reaction when the onset of unsafe conditions are detected. The invention directly detects, in real time, the power at a plurality of axial and radial locations within or about the core and provides a three-dimensional real-time core power output. The system processes those outputs together with a measure of core coolant inlet temperature, pressure and flow rate to calculate, in real time, the fuel centerline temperature, the heat transfer condition at the fuel elements' boundary and the rate of power change within the core.

Nuclear reaction protection system

A system for measuring the power distribution in a reactor core includes a plurality of gamma detectors disposed outside of the reactor vessel which houses the reactor core. The gamma detectors correspond in number to the number of instrumentation tubes in the fuel assemblies in the reactor core to be sampled. A first plurality of separate flow branches connect the instrumentation tubes with the gamma detectors for routing the flow of coolant from the instrumentation tubes to the gamma detectors so that the gamma detectors can measure the .sup.16 N decay gamma activity in the respective instrumentation tubes of the fuel assemblies. A second plurality of separate flow branches connect a cold leg of the reactor coolant system with the gamma detectors for routing the flow of coolant from the cold leg to the gamma detectors so that the gamma detectors can measure the background gamma activity in the respective instrumentation tubes of the fuel assemblies. Control valves interposed in the first and second pluralities of flow branches are operable to select communication of one or the other of the flows of coolant to the gamma detectors from either the instrumentation tubes or the cold leg.

Power distribution measuring system employing gamma detectors outside of

A method and apparatus for removably attaching a top nozzle to a nuclear fuel assembly to permit easy access to the fuel rods. The quick disconnect top nozzle structure includes guide thimbles which are clearance fitted into an adapter plate of the top nozzle. Load collars are attached to the guide thimbles to support compressive loads such as those imposed by holddown springs. Tensive forces, such as lift forces, are transferred through the top nozzle into peripheral straps of a top spacer grid. The peripheral straps include extensions which resiliently latch onto the top nozzle for ease of assembly and disassembly.

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Chapin, SC, United States of America

David L Stucker