Westinghouse Electric Company LLC

Westinghouse Electric Sweden Ab

Sumit Ray

Edward Jean Lahoda

Peng Xu

Zeses E Karoutas

Radu O Pomirleanu

Robert L Oelrich

Michael J Hone

Kumar Sridharan

Greg Johnson

Benjamin R Maier

Ho Q Lam

Frank A Boylan

Raymond E Schneider

Mitchell E Nissley

Lars Hallstadius

Jason P Mazzoccoli

Carroll J Long, Jr

Jonathan Wright

Fausto Franceschini

Zeses Karoutas

Hemant Shah

Grant L Eddy

Mikael Jolkkonen

Javier Romero

Radu Pomirleanu

A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of GdO, Ir, BC, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.

Control rods for light water reactors

A zirconium alloy cladding tube for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions is described. The cladding tube has a coating uniformly deposited thereon. The coating, which may be up to 300 microns thick, is selected from the group consisting of chromium, a chromium-based alloy, and combinations thereof.

Cold spray chromium coating for nuclear fuel rods

A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500&#xb0; C. that does not form a eutectic with a melting point less than 1500&#xb0; C., and may further include a cladding material having a melting point greater than 1500&#xb0; C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of GdO, Ir, BC, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.

An improved testing and data gathering method is described herein with reference to testing a new fuel, as an exemplary component to be tested for licensure purposes. The method includes generally: generating models for the new system; making samples and getting them accepted for a reactor; and testing the samples in a test or commercial reactor until the exposure time is reached for the expected cycle length of the fuel at final use. The method is preferably done concurrent to submitting a license application for commercial use of the new component to the relevant government body to expedite license testing review.

Integration of real-time measurements and atomistic modeling to license nuclear components

A method is provided for coating the substrate of a component, such as a zirconium alloy cladding tube, for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions. The method includes heating a pressurized carrier gas to a temperature between 200&#xb0; C. and 1200&#xb0; C., adding chromium or chromium-based alloy particles having an average diameter of 20 microns or less to the heated carrier gas, and spraying the carrier gas and particles onto the substrate at a velocity, preferably from 800 to 4000 ft./sec. (about 243.84 to 1219.20 meters/sec.), to form a chromium and/or chromium-based alloy coating on the substrate to a desired thickness.

The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.

Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications

The present invention relates to nuclear fuel compositions including triuranium disilicide. The triuranium disilicide includes a uranium component which includes uranium-235. The uranium-235 is present in an amount such that it constitutes from about 0.7% to about 5% by weight based on the total weight of the uranium component of the triuranium disilicide. The nuclear fuel compositions of the present invention are particularly useful in light water reactors.

Triuranium disilicide nuclear fuel composition for use in light water reactors

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Columbia, SC, United States of America

Sumit Ray