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
US10354767B2 · kind B2 · utility
Assignee
Inventors
Key dates
| Filing date | Apr 4, 2014 |
| Grant date | Jul 16, 2019 |
| Priority date | — |
| Expiry date | Jan 12, 2035 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A method for simulating the flow of a fluid in a vessel of a nuclear reactor is provided. The nuclear reactor includes the vessel and a core inside the vessel, the core including nuclear fuel assemblies, each one extending in an axial direction, including nuclear fuel rods and a grid for maintaining the rods, and being spaced apart from another by a clearance between the grids in a transverse direction.This method for simulating a fluid flow in the vessel of a nuclear reactor includes determining of head loss coefficients in the core, and computing the fluid pressure and speed component(s) in the core using the equation: ∇P=−K×V where P is the component of the fluid pressure, K is a matrix including the determined head loss coefficients, and V is a vector including the fluid speed component(s).A transverse head loss coefficient in the assemblies is determined from a transverse Reynolds number, and an axial head loss coefficient in the clearance is from the dimension of the clearance in the transverse direction.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.