Inventor

KROPACZEK DAVID JOSEPH

US24 patents

⚠️ This page may combine multiple inventors who share the name “KROPACZEK DAVID JOSEPH”. Patents are grouped by organization below to help distinguish them — per-person disambiguation is on the roadmap.

KROPACZEK DAVID JOSEPH

GLOBAL NUCLEAR FUEL AMERICAS

In-cycle shuffle

Method and arrangement for determining nuclear reactor core designs

Method of determining a fresh fuel bundle design for a core of a nuclear reactor

Method of determining nuclear reactor core design with reduced control blade density

Methods for evaluating robustness of solutions to constraint problems

Method and arrangement for developing rod patterns in nuclear reactors

Method and apparatus for evaluating a proposed solution to a constraint problem

Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors

Method and arrangement for developing core loading patterns in nuclear reactors

Method of improving nuclear reactor performance

Method and apparatus for adaptively determining weight factors within the context of an objective function

Method, arrangement and computer program for determining standardized rod types for nuclear reactors

Method and apparatus for facilitating recovery of nuclear fuel from a fuel pool

Systems and methods of predicting a critical effective k for a nuclear reactor

Method and apparatus for creating and editing a nuclear reactor core loading template

GEN ELECTRIC

Method and apparatus for evaluating robustness of proposed solution to constraint problem and considering robustness in developing a constraint problem solution

System and method for continuous optimization of control-variables during operation of a nuclear reactor

Method of determining margins to operating limits for nuclear reactor operation

Method and apparatus for moving nuclear fuel

KROPACZEK DAVID JOSEPH

Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria

Method for improving energy output of a nuclear reactor, method for determining natural uranium blanket layer for a fuel bundle, and a fuel bundle having a variable blanket layer

Method and system for designing a nuclear reactor core for uprated power operations

RUSSELL II WILLIAM EARL

Method for predicted reactor simulation

GLOBAL NUCLEAR FUELS AMERICAS LLC

Method and apparatus for evaluating a proposed solution to a constraint problem for a nuclear reactor involving channel deformation