Three-dimensional thermal-hydraulic analysis method and system for reactor core
US-2026018310-A1 · Jan 15, 2026 · US
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Thermo-hydraulic simulations
Thermo-hydraulic simulations · Cooperative Patent Classification (CPC)
Computing, optics, measurement, and control technologies.
Related technology areas
Mapped technology topics for this CPC code.
| Metric | Value |
|---|---|
| CPC code | G21D3/005 |
| Official title | {Thermo-hydraulic simulations} |
| Display label | Thermo-hydraulic simulations |
| Total patents | 23 |
Filing trend
Year-over-year patent counts classified under this CPC code.
Filing activity over the last five years is rapidly declining.
| Year | Patents |
|---|---|
| 2015 | 3 |
| 2016 | 4 |
| 2017 | 1 |
| 2018 | 1 |
| 2019 | 4 |
| 2021 | 2 |
| 2023 | 3 |
| 2024 | 3 |
| 2025 | 1 |
| 2026 | 1 |
Representative patents
Representative publications under this CPC code from precomputed stats, or recent filings when stats are unavailable.
Method for analyzing severe accident at nuclear power plant by using modular analysis code
US-2025029741-A1 · Jan 23, 2025 · US
Methods and systems for nuclear reactor design using fuel-cladding thermo-mechanics analysis
US-2024304350-A1 · Sep 12, 2024 · US
Method of evaluating thermal-hydraulic analysis of containment facility and computer program for executing the method
US-2024177878-A1 · May 30, 2024 · US
Methods for prediction of neutronics parameters using deep learning
US-2024062075-A1 · Feb 22, 2024 · US
Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability
US-11837372-B2 · Dec 5, 2023 · US
Method for analyzing severe accident in nuclear reactor based on advanced particle method
US-2023368934-A1 · Nov 16, 2023 · US
Computer-Based Simulation Methods for Boiling Water Reactors (BWR)
US-2023142755-A1 · May 11, 2023 · US
Enhanced neutronics systems
US-11157665-B2 · Oct 26, 2021 · US
Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability
US-2021225538-A1 · Jul 22, 2021 · US
Device for and method of reconstructing axial measurement values in nuclear fuel
US-10373721-B2 · Aug 6, 2019 · US
Methods for simulating the flow of a fluid in a vessel of a nuclear reactor and for calculating the mechanical deformation of assemblies of a nuclear reactor core, and associated computer program products
US-10354766-B2 · Jul 16, 2019 · US
Methods for simulating the flow of a fluid in a vessel of a nuclear reactor and for calculating the mechanical deformation of assemblies of a nuclear reactor core, and associated computer program products
US-10354767-B2 · Jul 16, 2019 · US
Simulation construction method for the measurement of control rod insertion time
US-10192006-B2 · Jan 29, 2019 · US
Plant operation assistance system and plant operation assistance method
US-2018247721-A1 · Aug 30, 2018 · US
Device for and method of reconstructing axial measurement values in nuclear fuel
US-2017200516-A1 · Jul 13, 2017 · US
Enhanced neutronics systems
US-2016321383-A1 · Nov 3, 2016 · US
Enhanced neutronics systems
US-9424376-B2 · Aug 23, 2016 · US
Methods for Simulating the Flow of a Fluid in a Vessel of a Nuclear Reactor and for Calculating the Mechanical Deformation of Assemblies of a Nuclear Reactor Core, and Associated Computer Program Products
US-2016042822-A1 · Feb 11, 2016 · US
Methods for simulating the flow of a fluid in a vessel of a nuclear reactor and for calculating the mechanical deformation of assemblies of a nuclear reactor core, and associated computer program products
US-2016042823-A1 · Feb 11, 2016 · US