Westinghouse Electric Corporation

Westinghouse Electric Company LLC

George P Sabol

John P Foster

Robert J Comstock

Samuel G McDonald

Samuel A Worcester

Robert F Barry

Charles S Cook

William A Byers

Joseph J Nemeth

Robert L Ammon

Francis Cellier

Merle A Parker

Raymond W Buckman

William A Jacobsen

Isabel K Lloyd

Donald W Parker

John I Nurminen

Richard D Reid

Samuel G McDonald Iii

Sun-Keun Hwang

Miklos Kamandi

Joseph W Kormuth

A reactor coolant system of a pressurized water nuclear reactor with fuel assemblies in the core is simultaneously shutdown and decontaminated in less than 90 hours after the shutdown is initiated. A LOMI or Can-Derem decontamination reagent is added to reactor coolant to reduce iron and nickel in oxidized coatings before removing dissolved hydrogen and reducing the gamma emitting activity of the reactor coolant.

Pressurized water reactor shutdown method

Finger manipulatable game with movable components

This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200.degree.-1300.degree. F., and to a beta quench two steps prior to final size.

Method of producing zirlo material for light water reactor applications

Zirlo material for light water reactor applications

A method of producing enhanced radial texture in zirconium alloy tubing suitable for use in forming cladding for nuclear fuel rods is provided. The tubing production method described herein employs a combination of mechanical expansion and heat treatment steps in the final stage of tubing formation to produce a single peak radial texture in the tubing, thereby imparting enhanced resistance to pellet-cladding-interaction to the finished tubing. The tubing is preferably processed to a diameter within less than about 10 to 20% of the desired final diameter, annealed, and expanded less than about 10 to 20% to the desired final diameter, thereby producing a unique radial texture in the finished tubing. In an alternative method, the finally expanded tubing is subjected to a final recrystallization anneal to produce a significantly enhanced split radial texture.

Single peak radial texture zircaloy tubing

A method of fabricating intermetallic compounds of TiAl and TiAl.sub.3 into shapes including a foil utilizing an arc spray process in which bimetalic titanium aluminum or low titanium aluminum and low aluminum titanium wires of the proper proportions are used to form an intermetallic compound overlay, which is densified to form the shape.

Method of fabricating shaped brittle intermetallic compounds

The present invention is a method of rapidly and reproducibly checking the quality of zirconium base material welds and heat affected zones. In this method, weldment samples are immersed in an elevated temperature fused salt bath for a time period sufficient, at the bath temperature selected, to produce an essentially black oxide film in acceptable quality welds while producing a scaling oxide in unacceptable welds.

Rapid corrosion test for zirconium and zirconium alloy weldments

This is a process for producing material for lining reactor fuel element claddings. Rather than using unalloyed zirconium, this invention provides for an alloy liner for the cladding. The process uses electron beam melting of zirconium, to give very low metallic impurities to reduce solid solution strengthening and second phase formation and property variability from lot to lot, while using alloying to reduce the susceptibility to steam corrosion. Preferably, oxygen is controlled to a low level as well, to provide a low, but fabricable, hardness in the alloyed liner material.

Process for the control of liner impurities and light water reactor

This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.

Zirconium alloy fuel cladding resistant to PCI crack propagation

A method of producing tubing composed of material, such as zirconium and alloys thereof, having a hexagonal close-packed crystal structure is provided which increases the radial texture or orientation of basal poles in the crystal structure of the material. The method includes intermediate and final stages. In the intermediate stage, multiple tubing reductions are performed, which each causes tubing wall thickness and diameter reduction and axial elongation, and a recrystallization anneal is performed following each of the tubing reductions. In the final stage, a last tubing reduction is performed, which causes tubing wall thickness and diameter reduction and axial elongation, and a final anneal is performed following the last tubing reduction. Also, in the intermediate stage, an expansion of the tubing diameter is performed following any one of the multiple tubing reductions and associated recrystallization anneals and then a recrystallization anneal is performed following the diameter expansion and before a next following tubing reduction in either of the intermediate and final stages of producing the tubing. The diameter expansion is an increase of from about five to twelve percent of the diameter of the tubing prior to the diameter expansion. The recrystallization anneal following the diameter expansion is at about 1250 degrees F. The tubing diameter expansion and recrystallization anneal result in enhanced texture of the finished tubing after completion of the final stage.

Texture enhancement of metallic tubing material having a hexagonal

An elongated nuclear fuel cladding tube is provided with at least two annular concentric layers which are bonded to each other. The inner layer is composed of a zirconium base alloy. The outer layer is composed of a titanium base material exhibiting excellent corrosion resistance in elevated temperature and pressure aqueous environments.

Composite nuclear fuel cladding tubing and other core internal

A nuclear fuel cladding tube composed of a single zirconium base alloy is provided preferably with a cold worked and stress relieved microstructure throughout. The cladding is characterized by excellent aqueous corrosion resistance as well as excellent resistance to PCI crack propagation. The alloy is selected from a group of zirconium base alloys containing tin, iron, chromium, and/or nickel and low levels of impurities.

PCI resistant light water reactor fuel cladding

Processes for the rapid alpha annealing of zirconium based articles are described. These processes utilize induction heating to rapidly heat a worked zirconium based article to an elevated temperature after which it is then cooled. Time at the selected elevated temperature is less than about 1 second, and preferably essentially zero. Stress relieving of cold pilgered Zircaloy may be performed by induction heating to a temperature between about 540.degree. and about 650.degree. C. Partial recrystallization annealing of cold pilgered Zircaloy may be performed by induction heating to a temperature between about 650.degree. and about 760.degree. C. Full alpha recrystallization annealing of cold pilgered Zircaloy may be performed by induction heating to a temperature between about 760.degree. and about 900.degree. C.

Annealing of zirconium based articles by induction heating

It has been found that modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.

Zirconium alloy products

The crystallographic texture of metallic tubular articles is characterized by an X-ray diffraction technique where X-rays are directed onto the surface of the tubular article and diffracted X-rays detected by use of a position-sensitive detector. By effecting relative movement of the tubular article and the X-ray source in both a rotational direction about the axis of the tube and in an axial direction, and measuring intensities from multiple Bragg peaks of the diffracted X-rays from a plurality of locations on the tube, the crystallographic texture of the tube is characterized.

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Murrysville, PA, United States of America

George P Sabol