Bwxt Mpower, Inc.

Bwxt Nuclear Operations Group, Inc.

Bwxt Canada Ltd.

Bwxt Nuclear Energy, Inc.

Bwx Technologies, Inc.

Babcock & Wilcox Mpower, Inc.

Babcock & Wilcox Nuclear Energy, Inc.

Bwxt Foreign Holdings, LLC

Babcock Wilcox Canada Ltd.

Matthew W Ales

Scott James Shargots

Michael J Edwards

Andrew C Whitten

John Dexter Malloy, Iii

Ronald C Watson

James Brian Inman

Lewis A Walton

Paul K DeSantis

Brett T Goodyear

Michael S Berthold

Kevin J Stambaugh

Billy E Bingham

John P McLaughlin

Christopher Douglas Dodd

Allan R Mackovjak

Jason G Williams

Sean M Boyle

Paul K Desantis

John P Mclaughlin

Christopher D Dodd

John D Malloy

Robert T Fortino

Nick Idvorian

Yuanming R Li

Jeffrey C Millman

Roy McGillvray

John D Iii Malloy

Jason G William

James B Inman

Roy Mcgillivray

A nuclear reactor comprises a nuclear reactor core disposed in a pressure vessel. An isolation valve protects a penetration through the pressure vessel. The isolation valve comprises: a mounting flange connecting with a mating flange of the pressure vessel; a valve seat formed into the mounting flange; and a valve member movable between an open position and a closed position sealing against the valve seat. The valve member is disposed inside the mounting flange or inside the mating flange of the pressure vessel. A biasing member operatively connects to the valve member to bias the valve member towards the open position. The bias keeps the valve member in the open position except when a differential fluid pressure across the isolation valve and directed outward from the pressure vessel exceeds a threshold pressure.

Integral vessel isolation valve

Refueling of a nuclear reactor () includes removing a fuel assembly (). The removal method includes lowering a lifting tool () of a crane () onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements () that surround and vertically overlap a portion () of a control rod assembly () extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features () at the top of the fuel assembly to connect the lifting tool with the fuel assembly. The connected fuel assembly is moved into a spent fuel pool () using the crane, and the lifting tool is disconnected from the top of the fuel assembly by unlocking the downwardly extending elements from the corresponding mating features at the top of the fuel assembly.

Nuclear reactor refueling methods and apparatuses

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 nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.

Self-supporting radial neutron reflector

A method including providing an internal control rod drive mechanism (CRDM) including an electric motor and a support surface including sealed electrical connectors electrically connected with the electric motor to deliver electrical power to the electrical motor, installing the internal CRDM inside a nuclear reactor, the installing including placing the support surface of the internal CRDM onto a support element inside the nuclear reactor, the placing causing sealed electrical connectors disposed on the support element to mate with the sealed electrical connectors on the support surface of the internal CRDM, wherein the nuclear reactor contains coolant water and the installing is performed with the internal CRDM submerged in the coolant water and the seals of the sealed electrical connectors of the internal CRDM and the support element are effective to prevent coolant water ingress into the sealed electrical connectors.

CRDM internal electrical connector and method of use thereof

In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (), a nuclear reactor core () disposed in the pressure vessel, and a vertically oriented hollow central riser () disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) () disposed in the pressure vessel includes vertical tubes () arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet () and a steam outlet (). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.

Compact nuclear reactor with integral steam generator

A control rod drive mechanism (CRDM) includes a lifting rod supporting a control rod and a holding mechanism comprising an electromagnetic circuit with magnetic poles drawn together when the electromagnetic circuit is energized to hold the lifting rod. The hold is released upon de-energizing the electromagnetic circuit. A translation mechanism linearly translates the lifting rod held by the holding mechanism. The holding mechanism may include a non-magnetic spacer between the magnetic poles that defines a gap between the drawn together magnetic poles. The translation mechanism may include latches configured to engage an upper end of the lifting rod, and the holding mechanism draws the magnetic poles together to hold the latches engaged with the upper end of the lifting rod. A four-bar cam assembly may be used to cam the latches closed in response to a vertical actuation force applied to the cam bars.

CRDM designs with separate SCRAM latch engagement and locking

A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.

Method of forming a support structure for a control rod assembly of a nuclear reactor

A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.

CRDM with separate scram latch engagement and locking

Growing community of inventors

Forest, VA, United States of America

Matthew W Ales