Patent Assignment
Reel/Frame 066380/0599
Release of Security Interest in Patents
Recorded: 2024-01-30
Pages: 52
Assignor
BANK OF MONTREAL, AS COLLATERAL AGENT
Executed: 2024-01-25
Assignees
WESTINGHOUSE ELECTRIC COMPANY LLC
1000 WESTINGHOUSE DRIVE, CRANBERRY TOWNSHIP, PENNSYLVANIA, 16066
BHI ENERGY I SPECIALTY SERVICES LLC
2005 NEWPOINT PKWY, SUITE 200, LAWRENCEVILLE, GEORGIA, 30043
Covered Properties
(357)
Eddy Current Data Union
Health Monitoring Display System for a Complex Plant
Component Interface Module
Control System Display for Monitoring a Complex Process
Method of Operating a Nuclear Power Plant at Multiple Power Levels
Patent:
6,674,826 →
Application:
10/252,496 →
Subcritical Reactivity Measurement Method
Seal Arrangement for in-Core Instrument Housing
Method of Closing a Pressure Vessel
Method of Establishing a Nuclear Reactor Core Fuel Assembly Loading Pattern
Reactor Pressure Vessel
Unirradiated Nuclear Fuel Component Transport System
Patent:
6,748,042 →
Application:
10/424,480 →
High Energy Absorption Top Nozzle for a Nuclear Fuel Assembly
Patent:
6,738,447 →
Application:
10/444,469 →
Crud-Resistant Nuclear Fuel Cladding
Patent:
6,813,329 →
Application:
10/459,777 →
Miniature Manipulator for Servicing the Interior of Nuclear Steam Generator Tubes
Pressurized Water Reactor Shutdown Method
Nondestructive Examination of High Pressure Turbine Cylinders
Patent:
6,886,407 →
Application:
10/646,136 →
Method for Calibrating Steam Generator Water Level Measurement
Nuclear Reactor Fuel Assemblies
Head Assembly
Bwr Inspection Manipulator
Method of Operating a Nuclear Power Plant at Multiple Power Levels
Nuclear Fuel Assembly Debris Filter Bottom Nozzle
Method of Inspecting a Heat Exchanger and Computer Program Product for Facilitating Same
Nonintrusive Method for the Detection of Concealed Special Nuclear Material
Jet Pump Assembly Repair Method
Method for Controlling Steam Generators
Patent:
6,886,502 →
Application:
10/874,666 →
Nuclear Fuel Assembly Protective Grid
Reactor Pressure Vessel
Method and Algorithm for Searching and Optimizing Nuclear Reactor Core Loading Patterns
An Eddy Current Method of Inspecting a Pressure Vessel Shell
Device and Method for Ultrasonic Inspection Using Profilometry Data
Helically Fluted Tubular Fuel Rod Support
Film Riding Shaft Seal
System and Method for Determining Fluctuating Pressure Loading on a Component in a Reactor Steam Dome
Spectroscopy-Based Safety System and Method for a Vacuum Arc Remelt Furnace
Gas Phase Electrolyzer Process for Producing Hydrogen
Advanced Gray Rod Control Assembly
Printed Circuit Card
Patent:
7,386,086 →
Application:
11/242,171 →
Over Temperature and Over Power Delta Temperature Operating Margin Recovery Method and Reactor System Employing the Same
Patent:
7,596,198 →
Application:
11/367,001 →
Shipping Package Up-Ender
Method for Analysis of Pellet-Cladding Interaction
Nuclear Fuel Assembly Control Rod Drive Thimble to Bottom Nozzle Connector
Solid State Reversing Ac Motor Starter with Dc Power Source
Current Limiting Dc Motor Starter Circuit
On-Line Testable Solid State Reversing Dc Motor Starter
Steam Generator Nondestructive Examination Method
Steam Generator Loose Parts Collector Weir
Tube-In-Tube Threaded Dashpot End Plug
Computerized Procedures System
Nuclear Fuel Assembly
Method of Assessing the Performance of a Steam Generator
Unirradiated Nuclear Fuel Component Transport System
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Method of Applying a Burnable Poison Onto the Exterior of Nuclear Rod Cladding
Upper Internals Arrangement for a Pressurized Water Reactor
Nuclear Reactor Control Rod Spider Assembly
Nuclear Reactor Vessel Fuel Thermal Insulating Barrier
Nuclear Reactor Downcomer Flow Deflector
Hydrogen Generation Process with Dual Pressure Multi Stage Electrolysis
Nuclear Reactor Robust Gray Control Rod
Nuclear Reactor Internals Alignment Configuration
Nuclear Reactor Alignment Plate Configuration
Pipe Clamp
Permanent Seal Ring for a Nuclear Reactor Cavity
Patent:
7,813,464 →
Application:
11/952,358 →
Eddy Current Data Interpolation/Extrapolation
Method of Improving the Spent Nuclear Fuel Burnup Credit
Cartridge Type Vortex Suppression Device
Nuclear Reactor Fuel Assembly
Advanced Logic System
Patent:
7,870,299 →
Application:
12/026,703 →
Pressurized Water Reactor Flow Skirt Apparatus
Advanced Gray Rod Control Assembly
Patent:
8,537,962 →
Application:
12/028,119 →
Neutron Absorber Consisting of Refractory Metal Infused with Discrete Neutron Absorber
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Steam Generator Dual System Sludge and Loose Parts Collector
Nuclear Fuel Assembly with a Lock-Support Spacer Grid
Reinforcement for a Nuclear Fuel Assembly
Nuclear Core Component Hold-Down Assembly
Fuel Rod Internal Pressure Measurement
Steam Generator Dual Head Sludge Lance and Process Lancing System
Enhanced Steam Dump (Bypass) Control System
Patent:
7,742,555 →
Application:
12/172,688 →
Reactor Dosimetry Applications Using a Parallel 3-D Radiation Transport Code
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Hatch Mechanical Locking System
Neutron Shielding Panels for Reactor Pressure Vessels
Subcritical Reactivity Measurement Method
Tube-In-Tube Threaded Dashpot End Plug
Failure Detection and Mitigation in Logic Circuits
Nuclear Fuel Assembly with Pivot Dimpled Grids
Process for Adding an Organic Compound to Coolant Water in a Pressurized Water Reactor
Non-Destructive Pipe Scanner
Modular Plate and Shell Heat Exchanger
Pipe Scanner
Two Step Dry UO2 Production Process Utilizing a Positive Sealing Valve Means Between Steps
Nuclear Fuel Assembly Protective Bottom Grid
Dynamic Port for Measuring Reactor Coolant Pump Bearing Oil Level
Reactor Coolant Pump Motor Load-Bearing Assembly Configuration
Helically Fluted Tubular Fuel Rod Support
Domed Diaphragm / Insert Plate for a Pressure Vessel Access Closure
Control Rod Drive Outer Filter Removal Tool
Wireless Transmission of Nuclear Instrumentation Signals
An Eddy Current Inspection Probe for Inspecting the Interior of a Tubular Member
Nuclear Fuel Assembly Support Grid
Steam Generator Nondestructive Examination Method
Thermally Activated Shutdown Seals for Rotatable Shafts
Core Shroud Corner Joints
Electrical Connector Assembly, Test Lead Assembly Therefor, and Associated Method
Upper Internals Arrangement for a Pressurized Water Reactor
Inspection Mode Switching Circuit
Process for Application of Lubricant to Fuel Rod During Fuel Assembly Loading Process
Expansion Gap Radiation Shield
Protective Grid Attachment
Method of Processing Steam Generator Tubes of Nuclear Power Plant
Method of Modeling Steam Generator and Processing Steam Generator Tube Data of Nuclear Power Plant
Enhanced Steam Dump (Bypass) Control System
Dual Drive Winch and Nuclear Reactor Vessel Maintenance Apparatus Employing Same
Under Vessel Local Power Range Monitor Exchange Tool
Digital Nuclear Control Rod Control System
Triuranium Disilicide Nuclear Fuel Composition for Use in Light Water Reactors
Reactor Head Seismic Support Tie Rod System
System and Method for Removal of Dissolved Gases in Makeup Water of a Water-Cooled Nuclear Reactor
System for Exchanging a Component of a Nuclear Reactor
Alternate Feedwater Injection System to Mitigate the Effects of Aircraft Impact on a Nuclear Power Plant
Nondestructive Inspection Method for a Heat Exchanger Employing Adaptive Noise Thresholding
Primary Neutron Source Multiplier Assembly
Calibration Detection System and Method
Method for Automated Position Verification
Nuclear Fuel Assembly Hold Down Spring
Unirradiated Nuclear Fuel Component Transport System
Advanced Logic System
Patent:
8,156,251 →
Application:
12/914,724 →
Advanced Logic System Diagnostics and Monitoring
Patent:
8,554,953 →
Application:
12/914,737 →
Wedge Positioning Apparatus for Jet Pump Assemblies in Nuclear Reactors
Miniature Sludge Lance Apparatus
Top Guide Inspection Fixture
Pressurizer with a Mechanically Attached Surge Nozzle Thermal Sleeve
Nuclear Reactor Automatic Depressurization System
Anti-Vibration Tube Support Plate Arrangement for Steam Generators
Nuclear Fuel Rod Plenum Spring Assembly
Wireless in-Core Neutron Monitor
Neutron Source Assembly
Noise and Vibration Mitigation System for Nuclear Reactors Employing an Acoustic Side Branch Resonator
Nuclear Reactor Cavity Arrangements for Ice Condenser Plants
Method of Improving Wear and Corrosion Resistance of Rod Control Cluster Assemblies
Chemical Cleaning Method and System with Steam Injection
Control Rod Transfer Device
Minature Sludge Lance Apparatus
Minature Sludge Lance Apparatus
Miniature Sludge Lance Apparatus
Minature Sludge Lance Apparatus
Captive Screw Device and Method
Method and Composition for Removing Deposits
Control Rod Drive Shaft Unlatching Tool
Anti-Vibration Bar Clamping Tool and Method
Fuel Handling Area Passive Filtration Design
Methodology for Modeling the Fuel Rod Power Distribution Within a Nuclear Reactor Core
Zirconium Alloys with Improved Corrosion/Creep Resistance Due to Final Heat Treatments
Nuclear Steam Generator Steam Nozzle Flow Restrictor
Steam Generator Tube Lane Flow Buffer
Submersible Machine Structured to Carry a Tool to a Limited Access Location Within a Nuclear Containment
Tool for Delivery of Testing Element to a Limited Access Location Within a Nuclear Containment
Squib Control Circuit
Rod Position Detection Apparatus and Method
Anti-Clogging Steam Generator Tube Bundle
Method of Achieving Automatic Axial Power Distribution Control
Self-Contained Emergency Spent Nuclear Fuel Pool Cooling System
Semi-Portable Emergency Cooling System for Removing Decay Heat from a Nuclear Reactor
Method of Replacing Shroud of Boiling Water Nuclear Reactor, and Associated Apparatus
Nuclear Fuel Rod Pellet Stack Inspection
Full Spectrum Loca Evaluation Model and Analysis Methodology
Nuclear Reactor Internal Hydraulic Control Rod Drive Mechanism Assembly
Nuclear Reactor Internal Electric Control Rod Drive Mechanism Assembly
Nuclear Control Rod Position Indication System
Retention Apparatus Employing Wedge Element and Engagement Assembly for Use in a Nuclear Application
Support Apparatus for Supporting Dosimetry System in Proximity to Reactor Apparatus
Method of Detecting an Existence of a Loose Part in a Steam Generator of a Nuclear Power Plant
Demister Vane in Situ Cleaning Fixture
Passive Containment Air Cooling for Nuclear Power Plants
Additives for Heat Exchanger Deposit Removal in a Wet Layup Condition
Advanced First Core Fuel Assembly Configuration and Method of Implementing the Same
Underwater Robotic Venting and Inspection System
Instrumentation and Control Penetration Flange for Pressurized Water Reactor
Method of Refueling a Nuclear Reactor
Pressurizer Surge-Line Separator for Integral Pressurized Water Reactors
Inspection Mode Switching Circuit
Nuclear Control Rod with Flexure Joint
Pressurized Water Reactor Compact Steam Generator
Combined Core Makeup Tank and Heat Removal System for a Small Modular Pressurized Water Reactor
Small Modular Reactor Safety Systems
Process for Adding an Organic Compound to Coolant Water in a Pressurized Water Reactor
Dynamic Port for Measuring Reactor Coolant Pump Bearing Oil Level
Axial Flow Steam Generator Feedwater Dispersion Apparatus
Conduit Length Adjustment Apparatus and Method
Pipeline Clamp for Vibration Measurement
Method of Segmenting Irradiated Boiling Water Reactor Control Rod Blades
Method to Extract Tritium from Irradiated Boiling Water Reactor Control Rod Blades
Method to Reduce the Volume of Boiling Water Reactor Fuel Channels for Storage
Apparatus for Vertically Segmenting a Boiling Water Reactor Control Rod Blade
Automated Analysis Coverage Verification (Aacv)
Sliding Duct Connection
In-Core Instrument Thimble Assembly
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Optimized Flower Tubes and Optimized Advanced Grid Configurations
Signal Processing of Lamb Wave Data for Pipe Inspection
Heavy Radial Neutron Reflector for Pressurized Water Reactors
Method and Apparatus for the Shielded Relocation of a Nuclear Component
Apparatus and Method for Removing the Upper Internals from a Nuclear Reactor Pressurized Vessel
Method and Apparatus for Refueling a Nuclear Reactor Having an Instrumentation Penetration Flange
Passive System for Cooling the Core of a Nuclear Reactor
Systems and Methods for Generating Power Employing Ves Air Supply Stored Energy
Alternate Passive Spent Fuel Pool Cooling Systems and Methods
Passive Power Production During a Nuclear Station Blackout
Method of Validating Nuclear Reactor in-Vessel Detector Output Signals
Tubesheet Walker for Heat Exchanger Inspections
Tubesheet Gripping Mechanism and Method
Nuclear Fuel Assembly Handling Apparatus
Filter for a Nuclear Reactor Containment Ventilation System
Mobile Boration System
Nuclear Reactor Bottom-Mounted Instrumentation Nozzle Repair Method
Eddy Current Inspection Probe
Apparatus and Method to Inspect, Modify, or Repair Nuclear Reactor Core Shrouds
Pump Seal with Thermal Retracting Actuator
Apparatus and Method to Control Sensor Position in Limited Access Areas Within a Nuclear Reactor
Nuclear Radiation Dosimeter Using Stress Induced Birefringence Changes in Fiber Optic Cables
Application:
13/803,104 →
Publication:
US 2014/0270039
Apparatus and Method to Inspect Nuclear Reactor Components in the Core Annulus, Core Spray and Feedwater Sparger Regions in a Nuclear Reactor
Access Hole Cover Ultrasonic Inspection Tooling
Apparatus to Switch Ultrasonic Signal Paths in a Moderately High Radiation Area
Reactor in-Core Instrument Handling System
Self Powered Neutron Detector
Method and Apparatus for Delivering a Tool to the Interior of a Heat Exchange Tube
Vver-1000 Fuel Assembly Bottom Nozzle
Systems and Methods for Spent Fuel Pool Subcriticality Measurement and Monitoring
Nuclear Fuel Assembly Having a Spacer Grid with One or More Seamless Corners
Systems and Methods for Steam Generator Tube Analysis for Detection of Tube Degradation
Method of Fastening a Captive Screw to a Panel
Captive Screw
Pump Seal with Thermal Retracting Actuator
Ion Chamber Radiation Detector
Sic Matrix Fuel Cladding Tube with Spark Plasma Sintered End Plugs
Jet Pump Diffuser Stack Repair
High Temperature Strength, Corrosion Resistant, Accident Tolerant Nuclear Fuel Assembly Grid
Wireless Transmission of Nuclear Instrumentation Signals
Method for Monitoring Boron Dilution During a Reactor Outage
Steam Generator Dual Head Sludge Lance
Rib-Type Roughness Design for Improved Heat Transfer in Pwr Rod Bundles
Targeted Heat Exchanger Deposit Removal by Combined Dissolution and Mechanical Removal
Ambient Temperature Decontamination of Nuclear Power Plant Component Surfaces Containing Radionuclides in a Metal Oxide
Pump Seal with Thermal Retracting Actuator
Steam Generator Sludge Lance Apparatus
Solid State Electrical Generator
Loop Dissolution System
Patent:
9,718,038 →
Application:
14/195,875 →
Apparatus for Passively Cooling a Nuclear Plant Coolant Reservoir
In-Containment Spent Fuel Storage to Limit Spent Fuel Pool Water Makeup
Reactor Internals Sensor Inserts
Patent:
9,922,737 →
Application:
14/203,679 →
KINETICALLY APPLIED GRADATED Zr-Al-C CERAMIC OR Ti-Al-C CERAMIC OR AMORPHOUS OR SEMI-AMORPHOUS STAINLESS STEEL WITH NUCLEAR GRADE ZIRCONIUM ALLOY METAL STRUCTURE
Double-Sealed Fuel Rod End Plug for Ceramic-Containing Cladding
Ceramic Reinforced Zirconium Alloy Nuclear Fuel Cladding with Intermediate Oxidation Resistant Layer
Low Pressure Drop Nuclear Fuel Assembly Bottom Nozzle
Deposition of a Protective Coating Including Metal-Containing and Chromium-Containing Layers on Zirconium Alloy for Nuclear Power Applications
Control Rod Guide Tube with an Extended Intermediate Guide Assembly
Thermo-Acoustic Nuclear Power Distribution Measurement Assembly
Method and Apparatus for Manipulating Equipment Inside a Steam Generator
Method for In-Core Instrumentation Withdrawal From the Core of a Pressurized Water Reactor
Pressurized Water Reactor Fuel Assembly
Apparatus and Method to Remotely Inspect Piping and Piping Attachment Welds
Electrical System, and Connection Device and Method of Powering a Switchgear Bus in an Electrical System
Deposition of Integrated Protective Material Into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Nuclear Fuel Assembly Support Grid
Ultrasonic Phased Array Transducer for the Nde Inspection of the Jet Pump Riser Welds and Welded Attachments
Magneto-Rheological Fluid Based Filter/Reflector
Mobile Boration System
Method for Refueling a Nuclear Reactor Having an Instrumentation Penetration Flange
Nuclear Fuel Assembly Support Feature
A Method of Accessing a Core of a Nuclear Reactor
Zirconium Alloys with Improved Corrosion/Creep Resistance Due to Final Heat Treatments
Zirconium Alloys with Improved Corrosion/Creep Resistance
Under Vessel Automated Work Platform Assembly
Total Integrated Tube Analysis
Chemical Process for Primary System Material Passivation During Hot Functional Testing of Nuclear Power Plants
Method for Measuring Bow/Twist of a Fuel Assembly
Corrosion and Wear Resistant Coating on Zirconium Alloy Cladding
Discharge Apparatus Usable for Determining Neutron Flux
Method of Servicing Modular Plate and Shell Heat Exchanger
Cryogenic System for Spent Nuclear Fuel Pool Emergency Cooling & Safety System
Thermal Retracting Actuator
Passive System for Cooling the Core of a Nuclear Reactor
Modular Electrochemical Machining Apparatus
Application:
14/936,751 →
Publication:
US 2017/0129030
Method for Shielded Relocation of a Nuclear Component
Advanced First Core Fuel Assembly Configuration
Multilayer Composite Fuel Clad System with High Temperature Hermeticity and Accident Tolerance
System Usable in Nuclear Environment for Providing Breathing Gas
Measurement Apparatus for Determining Compressive Loading That Will Be Applied to a Fuel Rod of a Pressurized Water Reactor
Hydraulic Apparatus and Hydraulic Appliance Usable Therein
Method for Delivering a Tool to the Interior of a Heat Exchange Tube
Top Nozzle and Pressurized Water Nuclear Reactor Including Same
Nuclear Control Rod Position Indication System
In-Containment Ex-Core Detector System
Spring Apparatus and Support Apparatus Usable in Nuclear Installation
Method of Detecting and Outputting Radiation Dose Rate Information
Holding Fixture to Assist in Assembly of Support Grid for Nuclear Fuel Rods and Method for Assembling Support Grid for Nuclear Fuel Rods
Remote Heat Removal System
Method of Removing Upper Internals from a Nuclear Reactor Pressurized Vessel
Reactor Coolant System Piping Temperature Distribution Measurement System
Apparatus and Method to Inspect Nuclear Reactor Components in the Core Annulus, Core Spray and Feedwater Sparger Regions in a Nuclear Reactor
Targeted Heat Exchanger Deposit Removal by Combined Dissolution and Mechanical Removal
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Nuclear Power Plant Containment Real-Time Remote Operations Management Employing Server and Client
Delivery Device Usable in Laser Peening Operation, and Associated Method
Pulsed Neutron Generated Prompt Gamma Emission Measurement System for Surface Defect Detection and Analysis
Patent:
9,528,952 →
Application:
15/156,757 →
Zirconium-Coated Silicon Carbide Fuel Cladding for Accident Tolerant Fuel Application
Method of Manufacturing a Sic Composite Fuel Cladding with Inner Zr Alloy Liner
Irradiation Target Handling Device for Moving a Target into a Nuclear Reactor
Method of Predicting Wear on Tubes of Steam Generator
Sic Matrix Fuel Cladding Tube with Spark Plasma Sintered End Plugs
Process for Manufacturing Sic Composite Ceramics
Tank Closure Cesium Removal
Alternate Passive Spent Fuel Pool Cooling Systems and Methods
Cold Spray Chromium Coating for Nuclear Fuel Rods
System and Process for Production and Collection of Radioisotopes
Nuclear Instrumentation System High Voltage Power Supply
Patent:
9,998,025 →
Application:
15/341,518 →
Hydrostatic Mechanical Face Seal
Patent:
9,920,839 →
Application:
15/361,755 →
Fuel Assembly with an External Dashpot Disposed Around a Guide Tube Portion
Apparatus for Degassing a Nuclear Reactor Coolant System
In-Core Transmitter Device Structured to Wirelessly Emit Signals Corresponding to Detected Neutron Flux
Recontamination Mitigation Method by Carbon Steel Passivation of Nuclear Systems and Components
Method of Manufacturing a Reinforced Nuclear Fuel Cladding Using an Intermediate Thermal Deposition Layer
Orbital Welder With Integrated Track And Gear Drive
Integration of Real-Time Measurements and Atomistic Modeling to License Nuclear Components
Spacer Grid Using Tubular Cells With Mixing Vanes
Fuel Assembly Arrangement for Retaining Fuel Rod End Plug to Bottom Nozzle
Thermal Retracting Actuator
Method of Detecting and Outputting Radiation Dose Rate Information
Nuclear Fuel Rod
Modular Plate and Shell Heat Exchanger
Ambient Temperature Decontamination of Nuclear Power Plant Component Surfaces Containing Radionuclides in a Metal Oxide
Corrosion and Wear Resistant Coating on Zirconium Alloy Cladding
Method of Predicting Wear on Tubes of Steam Generator
Steam Generator Sludge Lance Apparatus
Method to Pressurize Sic Fuel Cladding Tube Before End Plug Sealing by Pressurization Pushing Spring Loaded End Plug
Steam Generator Dual Head Sludge Lance
Method of Visually Outputting to a Worker During an Operation a Number of Parameters Pertaining to the Operation, and Associated Apparatus
Method of Detecting and Outputting Radiation Dose Rate Information
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
System and Process for Production and Collection of Radioisotopes
Nuclear Fuel Assembly Support Feature
Method of Installing an External Dashpot Tube Around a Control Rod Guide Tube in a Nuclear Fuel Assembly
Cold Spray Chromium Coating for Nuclear Fuel Rods
In-Containment Spent Fuel Storage to Limit Spent Fuel Pool Water Makeup
Apparatus and Method to Remotely Inspect Piping and Piping Attachment Welds
Ultrasonic Phased Array Transducer for the Nde Inspection of the Jet Pump Riser Welds and Welded Attachments
Real-Time Reactor Coolant System Boron Concentration Monitor Utilizing an Ultrasonic Spectroscpopy System
Delivery Device Usable in Laser Peening Operation, and Associated Method
Wirelessly Emitting Signals Corresponding to Detected Neutron Flux
Fuel Assembly Arrangement for Retaining Fuel Rod End Plug to Bottom Nozzle
Irradiation Target Handling Device for Moving a Target into a Nuclear Reactor
Spacer Grid Using Tubular Cells
Zirconium-Coated Silicon Carbide Fuel Cladding for Accident Tolerant Fuel Application
Method of Detecting an Existence of a Loose Part in a Steam Generator of a Nuclear Power Plant
Method to Pressurize Sic Fuel Cladding Tube Before End Plug Sealing by Pressurization Pushing Spring Loaded End Plug
Application:
17/347,311 →
Publication:
US 2021/0375494
Related Assignments
(7)
Other recorded transfers of the patents in this record — the chain of ownership.
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: CREDIT SUISSE AG, CAYMAN ISLANDS BRANCH, AS COLLATERAL AGENT
Reel/Frame 046708/0222 →
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: BANK OF MONTREAL, AS ADMINISTRATIVE AGENT
Reel/Frame 046708/0639 →
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: GOLDMAN SACHS BANK USA, AS COLLATERAL AGENT
Reel/Frame 046708/0332 →
Release of Security Interest in Patents
Aug 1, 2019
From: GOLDMAN SACHS BANK USA, AS COLLATERAL AGENT
To: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
Reel/Frame 049937/0032 →
Patent Security Agreement
May 27, 2022
From: WESTINGHOUSE ELECTRIC COMPANY LLC; BHI ENERGY I SPECIALTY SERVICES LLC
To: BANK OF MONTREAL, AS COLLATERAL AGENT
Reel/Frame 060791/0372 →
Security Interest
Jan 26, 2024
From: WESTINGHOUSE ELECTRIC COMPANY LLC; BHI ENERGY I SPECIALTY SERVICES LLC; STONE & WEBSTER, L.L.C. (FORMERLY STONE & WEBSTER, INC.)
To: DEUTSCHE BANK AG NEW YORK BRANCH, AS COLLATERAL AGENT
Reel/Frame 066373/0604 →
Release of Security Interest in Patents
Jan 30, 2024
From: CREDIT SUISSE AG, CAYMAN ISLANDS, AS COLLATERAL AGENT
To: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
Reel/Frame 066380/0392 →