General Electric Company

Ge-hitachi Nuclear Energy Americas LLC

Catherine Procik Dulka

Young Jin Kim

David Wesley Sandusky

John Frederick Ackerman

Rajasingh Schwartz Israel

Tianji Zhao

Kevin Henry Janora

Peter William Brown

James Edgar Burner

Glen Arthur MacMillan

Leland L Lantz

Mark Olaf Lenz

Gail E Dunning

Evan H Komito

Michael B McMahan

Richard Oran Kilgo

Edwin R Baker

Mark O Lenz

Rajasingh Swartz Israel

Example embodiments relate to a method and apparatus for reducing electrostatic deposition of charged particles on wetted surfaces that are exposed, periodically or substantially continuously, to high velocity fluid flow within a coolant flow path in a nuclear reactor. The method may include depositing a first or base dielectric layer and a second or outer dielectric layer on a conductive surface that forms a portion of a high velocity flow path to attain the apparatus. The first dielectric layer material is selected to provide improved adhesion and insulation to the conductive surface and the second dielectric layer material is selected to provide suitable adhesion to the first dielectric layer and improved corrosion and/or mechanical resistance in the anticipated operating environment.

Dielectric coating for surfaces exposed to high temperature water

A method of protecting a reactor component from fouling includes forming an oxide layer on a metal foil to achieve an antifouling liner. The antifouling liner may be manipulated into a shape that conforms to one or more surfaces of the reactor component that are contacted by a fluid during reactor operation. The metal foil portion of the antifouling liner is secured to the surface(s) of the reactor component by suitable means. As a result, the oxide layer portion of the antifouling liner is exposed to the fluid in the reactor, thereby reducing or preventing the fouling of the component.

Method of protecting reactor components from fouling

Disclosed is a method for reducing electrostatic deposition of charged particles on wetted surfaces that are exposed, periodically or substantially continuously to high velocity fluid flow within a coolant flow path in a nuclear reactor. The method includes depositing a first or base dielectric layer and a second or outer dielectric layer on a conductive surface that forms a portion of a high velocity flow path. The first dielectric layer material is selected to provide improved adhesion and insulation to the conductive surface and the second dielectric layer material is selected to provide suitable adhesion to the first dielectric layer and improved corrosion and/or mechanical resistance in the anticipated operating environment.

A jet pump for a nuclear reactor includes a riser and an inlet mixer having a set of nozzles and a mixing section for receiving coolant flow from the nozzles and suction flow from an annular space between the reactor vessel and the shroud core. To minimize or eliminate electrostatic deposition of charged particulates carried by the coolant on interior wall surface of the inlet-mixer of the jet pump, and also to inhibit stress corrosion cracking, the interior wall surfaces of the nozzles and mixing section are coated with a ceramic oxide such as TiO and Ta O to thicknesses of about 0.5-1.5 microns.

Apparatus and methods for protecting a jet pump nozzle assembly and inlet-mixer

Method of treating a surface of a steam line plug grip wherein the surface is subjected to chemical vapor deposition (CVD) treatment to introduce a hard oxide material into pores and cracks in the surface.

CVD treatment of hard friction coated steam line plug grips

An improved method for determining the nuclear radiation threshold of a non-metallic material with the aid of a computer is disclosed, in which differently irradiated samples of the material are subjected to thermogravimetric analysis. From the resultant pyrolytic weight-loss, temperature and elapsed time data, the reaction rates are determined for different orders of reaction values and are plotted against inverse temperature values to obtain the activation energy corresponding to each sample. By plotting activation energy against radiation dose for each sample, the radiation threshold of the material is obtained.

Method for determining the radiation threshold of non-metallic materials

Growing community of inventors

West Chester, PA, United States of America

Catherine Procik Dulka