Bwxt Nuclear Energy, Inc.

Bwxt Mpower, Inc.

Bwxt Advanced Technologies LLC

Bwxt Isotope Technology Group, Inc.

The Babcock & Wilcox Company

Babcock & Wilcox Mpower, Inc.

Babcock & Wilcox Technical Services Group, Inc.

James Brian Inman

Joshua J Bergman

Roger Dale Ridgeway

Matthew W Ales

Gary W Neeley

Scott James Shargots

John Dexter Malloy, Iii

Jonathan K Witter

Eric A Barringer

Jeremy Leslie Gustafson

Matt Ales

Russell R Jensen

Danny Galicki

Matt Krecicki

Ronald C Watson

Billy E Bingham

Andrew C Whitten

Ryan Z Ziegler

Ryan Trigg Swanson

Jason G Williams

Sean M Boyle

Earl Brian Barger

Craig D Gramlich

William Earl Russell, Ii

Erik T Nygaard

Timothy A Policke

Bryan Blake Wiggins

Christopher Sean Fewox

Stephen D Preite

Benjamin I Bishop

Barbara B Bohannon

William E Russell, Ii

Jonathan W Cirtain

Matthew P Levasseur

Joseph K Miller

Steve W Schilthelm

Michael J Edwards

Tyler A Edwards

Richard Forsythe Rochow

Robert Paul Martin

Charles Larry Fisher

Russell L Lake

James McNulty

Martin Reifschneider

John Smith

Daniel P Speaker

Curtis G Hamilton

Steven M Delessio

John D Malloy, III

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. Fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.

Carbide-based fuel assembly for thermal propulsion applications

In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.

Passive techniques for long-term reactor cooling

A process for producing a titanium-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a titanium source to provide a Ti—Mo composition. The Ti—Mo composition can be pH adjusted with a base to precipitate a plurality of Ti—Mo particulates.

Titanium-molybdate and method for making the same

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.

Plurality of layers form a nuclear fission reactor structure, each layer having an inner segment body, an intermediate segment body, and an outer segment body (each segment body separated by an interface). The layers include a plurality of cladding arms having involute curve shapes that spirally radiate outward from a radially inner end to a radially outer end. Chambers in the involute curve shaped cladding arm contain fuel compositions (and/or other materials such as moderators and poisons). The design of the involute curve shaped cladding arms and the composition of the materials conform to neutronic and thermal management requirements for the nuclear fission reactor and are of sufficiently common design and/or have sufficiently few variations as to reduce manufacturing complexity and manufacturing variability.

Fission reactor with segmented cladding bodies having cladding arms with involute curve shape

A dual shut-off valve including a valve body defining an interior cavity and a flow tube passing therethrough, an outer cylinder including a body portion defining an interior cavity and a through hole passing therethrough, the outer cylinder being rotatably disposed within the interior cavity of the valve body, and an inner cylinder including a body portion defining a through hole passing therethrough, the inner cylinder being rotatably disposed within the interior cavity of the outer cylinder, wherein the inner cylinder and the outer cylinder are both rotatable between a first position in which the through holes of the outer cylinder and the inner cylinder are aligned with the flow tube and a second position in which the through holes of the outer cylinder and the inner cylinder are transverse to the flow tube.

Dual shut-off valve

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. Continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.

A nuclear reactor has first and second plenum plates disposed in a pressure vessel. Both plenum plates have a plurality of apertures. The second plenum plate is parallel to the first plenum plate. A fuel element includes a fuel element coolant flow tube which extends through aligned apertures of the parallel plenum plates. A fuel element standoff spool is disposed about a portion of the fuel element coolant flow tube which is located between the plenum plates. The nuclear reactor is also usable in nuclear thermal propulsion.

Plenum plate standoff spools for separating a pair of plenum plates in a nuclear reactor

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC&#x2014;SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.

Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.

Method for design and additive manufacture of fission reactor core structure of inverted reactor

A control rod assembly for a nuclear reactor having a reactor core and a pressurized fluid source, including a control rod disposed within a control rod sleeve, a lead screw that is selectively secured to the control rod, a trip latch that is secured to a bottom end of the lead screw, the trip latch being selectively securable to a top end of the control rod, a control rod drive motor that is operably connected to the lead screw, and a valve that is in fluid communication with the pressurized fluid source of the nuclear reactor and is movable between a first position and a second position, wherein in the second position of the gas valve the trip latch is in an open position.

Space reactor gas assist control rod release mechanism

Universal inverted reactor

A desuperheating spray chamber for use in a rocket exhaust recovery system for a nuclear thermal propulsion rocket, including a substantially-cylindrical outer tank with an upper end including an entrance port and two exhaust ports, a substantially-cylindrical shroud extending downwardly from an inner surface of the upper end of the tank, an annular inner spray ring that is both disposed within and concentric with the shroud; and an annular outer spray ring that is disposed between a side wall of the outer tank and the shroud, the annular outer ring being concentric with the shroud.

Apparatus for desuperheating high temperature, high velocity steam

A control drum system for a nuclear reactor including a reactor core, including an ex-core reflector including a plurality of cylindrical apertures, a plurality of control drum assemblies, each control drum assembly including a drive shaft, a drum cylinder affixed to a bottom end of the drive shaft, and a planetary gear attached to a top end of the drive shaft, wherein each drum cylinder is rotatably received in a cylindrical aperture, a first control drum drive motor operably connected to a first control drum assembly, and an annular ring gear that is operably connected to the planetary gear of each of the control drum assemblies so that all the control drum assemblies rotate simultaneously.

Control drum system for use with nuclear reactors

Growing community of inventors

Forest, VA, United States of America

James Brian Inman