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

US10354766B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-10354766-B2
Application numberUS-201414782767-A
CountryUS
Kind codeB2
Filing dateApr 4, 2014
Priority dateApr 10, 2013
Publication dateJul 16, 2019
Grant dateJul 16, 2019

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

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  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A method for simulating the fluid flow in a vessel of a nuclear reactor is provided. The reactor includes a core inside the vessel, the core including a lower plate, an upper plate and fuel assemblies extending between the plates, and having a volume axially delimited by first and second interfaces corresponding to the plates. The method includes computing, for the core volume, the fluid pressure and speed, from an initial value of the speed or pressure in the first interface and respectively in the second interface, and using the fluid mass, movement quantity and energy balance equations. The method includes determining an additional volume inside the vessel, the additional volume being outside the core volume, axially at one end thereof and axially delimited by two interfaces, one of which is the first or second interface; and the computing, for the additional volume and using the equations, the pressure and speed, from an initial value of the speed or pressure in each of the interfaces of the additional volume.

First claim

Opening claim text (preview).

What is claimed is: 1. A method for simulating the flow of a fluid inside a vessel of a nuclear reactor, the nuclear reactor comprising the vessel and a core positioned inside the vessel, the vessel including a fluid inlet orifice and a fluid outlet orifice, the core including a lower plate, an upper plate and nuclear fuel assemblies extending in an axial direction between the lower and upper plates, the core having a volume delimited by first and second interfaces in the axial direction, the first and second interfaces respectively corresponding to the lower and upper plates, the fluid being able to flow inside the core between the assemblies, the method comprising, implementing by a computer including a processor and a memory associated with the processor, the following steps: computing, for the core volume, a pressure of the fluid and component(s) of a speed of the fluid, from an initial value of the speed or pressure of the fluid in the first interface and an initial value of the speed or pressure of the fluid in the second interface and using a fluid mass balance, a movement quantity balance and energy balance equations of the fluid; determining at least one additional volume inside the vessel, the additional volume being outside the core volume and situated at one of the ends thereof in the axial direction, the additional volume being delimited by two interfaces in the axial direction, one of the two interfaces of the additional volume being the first interface or the second interface; computing, for the additional volume and using the fluid mass balance, movement quantity balance and energy balance equations of the fluid, the pressure of the fluid and the component(s) of the speed of the fluid, from an initial value of the speed or pressure in one of the interfaces of the additional volume and an initial value of the speed or the pressure in the other of the interfaces of the additional volume, the computation of the pressure of the fluid and of the component(s) of the speed of the fluid is first done for a first volume among the additional volume and the core volume, and in particular in the interface among the first and second interfaces that is shared by the additional volume and the core volume, then the pressure of the fluid and the component(s) of the speed of the fluid is computed for the second volume among the additional volume and the core volume, the initial value of the speed or pressure at the interface shared by the additional volume and the core volume and for that computation step associated with the second volume being the value of the corresponding variable among the speed and the pressure previously computed at the interface for the first volume; and generating a simulation of the flow of the fluid inside the core such that the fluid is simulated to flow inside the core in accordance with the pressure of the fluid and the component(s) of the speed of the fluid computed for the core volume and the additional volume. 2. The method as recited in claim 1 , wherein the fluid mass balance, movement quantity balance and energy balance equations are respectively as follows: ⁢ ∂ ρ ∂ t + ∇ ( ρ ⁢ ⁢ V ) = S m ⁢ ⁢ ⁢ ∂ ( ρ ⁢ ⁢ V ) ∂ t + ∇ · ( ρ ⁢ ⁢ V ⊗ V ) = - ∇ P + ∇ · τ + ρ ⁢ ⁢ F + S i ⁢ ⁢ ∂ ( ρ ⁢ ⁢ E ) ∂ t + ∇ · [ ( ρ

Assignees

Inventors

Classifications

  • for evaluating statistical data {, e.g. average values, frequency distributions, probability functions, regression analysis (forecasting specially adapted for a specific administrative, business or logistic context G06Q10/04)} · CPC title

  • Cross-Sectional Technologies · mapped topic

  • G21D3/001Primary

    Computer implemented control · CPC title

  • Thermo-hydraulic simulations · CPC title

  • Nuclear fission reactors · CPC title

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What does patent US10354766B2 cover?
A method for simulating the fluid flow in a vessel of a nuclear reactor is provided. The reactor includes a core inside the vessel, the core including a lower plate, an upper plate and fuel assemblies extending between the plates, and having a volume axially delimited by first and second interfaces corresponding to the plates. The method includes computing, for the core volume, the fluid …
Who is the assignee on this patent?
Areva Np
What technology area does this patent fall under?
Primary CPC classification G21D3/001. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Jul 16 2019 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 1 related publication on this page (citations in our corpus or others sharing the same primary CPC).