A review of fretting study on nuclear power equipment

Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition

A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel ☆

https://hal.archives-ouvertes.fr/hal-01634319/document

Effects of gap size and excitation frequency on the vibrational behavior and wear rate of fuel rods

Assessment of wear coefficients of nuclear zirconium claddings without and with pre-oxidation ☆

Comparative study on rod fretting behavior of different spacer spring geometries

Disclosed is a fuel element for a pressurized water reactor, comprising a plurality of fuel rods (2) that are guided inside a plurality of axially spaced-apart spacers (4d) which are composed of grid webs (20). Each of said grid webs (20) forms a grid with a multitude of grid cells (6) which are disposed in rows and columns. The grid webs (20) are provided with flow-conducting means (26) for generating a cooling water current encompassing a transversal flow component that is oriented parallel to the spacer plane. According to the invention, at least one spacer (4) is composed of a multitude of subareas (50a-d), each of which is greater than one grid cell (6), while the flow-conducting means (26) are designed and distributed within the spacer (4) in such a way that in the wake above each subarea (50a-d), a transversal flow distribution is created which causes cooling water to be exchanged at least almost exclusively between secondary flow ducts (6) located within the subarea.

Fuel element for a pressurized water reactor

The invention relates to a fuel element (2) for a pressurized water nuclear reactor, in which fuel element (2) a multiplicity of fuel rods (6) which extend in a longitudinal direction (4) are guided in a plurality of spacers (8-I, 8-II) which are spaced apart from one another axially, the spacers (8-II) of an upper region (II) having a lower flow resistance in a transverse direction (16, 18), which is perpendicular to the longitudinal direction (4), than the spacers (8-I) of a lower region (I).

Fuel element for a pressurized water nuclear reactor

Study of Dynamics of a Tube Array under Cross Flow by Means of CFD-Simulation

A fuel assembly for a pressurized water nuclear reactor includes a multiplicity of fuel rods which extend in a longitudinal direction and are guided in a plurality of spacers that are spaced apart from one another axially. The spacers of an upper region have a lower flow resistance in a transverse direction perpendicular to the longitudinal direction, than the spacers of a lower region.

Mingmin Ren

Papers

Comparative study on rod fretting behavior of different spacer spring geometries

Fuel element for a pressurized water reactor

Fuel element for a pressurized water nuclear reactor

Study of Dynamics of a Tube Array under Cross Flow by Means of CFD-Simulation

Fuel assembly for a pressurized water reactor