The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium

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Total Pages : 52 pages
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Book Synopsis The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium by : J. E. Draley

Download or read book The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium written by J. E. Draley and published by . This book was released on 1957 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt: Alloys of uranium with niobium show good corrosion resistance in degassed, distilled water to about 315 degrees C. The alloys must be quenched from the gamma phase in order to have high temperature corrosion resistance. The corrosion resistance is destroyed by over-aging at temperatures as low as 350 degrees C. Of those tried, the alloy with best resistance to thermal aging is the uranium-5% zirconium-1.5% niobium alloy. At 290 degrees C, optimum heat treatment can result in a rate of corrosion of about 6 mg/cm sq/day. Certain moderate aging treatments, e.g., 400 degree C for two hours, result in improved corrosion resistance in the initial stages of corrosion. Alloys containing 3% niobium and small amounts of tin show promise. In addition to aging, the alloys are also sensitive to hydrogen content. Ultimate corrosion failure is believed due to absorption of corrosion product hydrodgen.

AEC-Euratom Conference on Aqueous Corrosion of Reactor Materials

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Total Pages : 474 pages
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Book Synopsis AEC-Euratom Conference on Aqueous Corrosion of Reactor Materials by :

Download or read book AEC-Euratom Conference on Aqueous Corrosion of Reactor Materials written by and published by . This book was released on 1960 with total page 474 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Uranium: Alloys and compounds. 1936-1958

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ISBN 13 :
Total Pages : 16 pages
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Book Synopsis Uranium: Alloys and compounds. 1936-1958 by : United States Dept. of Commerce. Office of Technical Services

Download or read book Uranium: Alloys and compounds. 1936-1958 written by United States Dept. of Commerce. Office of Technical Services and published by . This book was released on 1958 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 852 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 852 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Corrosion Properties of Zirconium-base Fuel Alloys

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Total Pages : 42 pages
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Book Synopsis The Corrosion Properties of Zirconium-base Fuel Alloys by : Sam Kass

Download or read book The Corrosion Properties of Zirconium-base Fuel Alloys written by Sam Kass and published by . This book was released on 1956 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 628 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1972 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Heat Transfer and Fluid Flow

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ISBN 13 :
Total Pages : 444 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Heat Transfer and Fluid Flow by : James M. Jacobs

Download or read book Heat Transfer and Fluid Flow written by James M. Jacobs and published by . This book was released on 1958 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: A total of 2519 annotated references to the unclassified report literature is presented. Subjects covered under heat transfer and fluid flow include radioinduced heating; boiling; boiler, evaporators, pump, and heat exchanger design; hydrodynamics; coolants and their properties; thermal and flow instrumentation; high temperature materials; thermal properties of materials; and thermal insulation. Subjects covered less completely include thermodynamics; aerodynamics; high temperature corrosion; corrosion specific to heat transfer systems; erosion; mass transfer; corrosion film formation and effects; coolant processing and radioactivity; radiation effects of heat transfer materials; and pertinent data of thermonuclear processes. Subject, report number availability, and author indexes are given.

Catalog of Technical Reports

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ISBN 13 :
Total Pages : 600 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Catalog of Technical Reports by : United States. Dept. of Commerce. Office of Technical Services

Download or read book Catalog of Technical Reports written by United States. Dept. of Commerce. Office of Technical Services and published by . This book was released on with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Corrosion of Uranium Alloys in High-Temperature Water

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Total Pages : pages
Book Rating : 4.:/5 (953 download)

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Book Synopsis Corrosion of Uranium Alloys in High-Temperature Water by :

Download or read book Corrosion of Uranium Alloys in High-Temperature Water written by and published by . This book was released on 1953 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In the search for a corrosion-resistant high-uraniumcontent alloy for use as core material in high-temperature-water-moderated reactors, the corrosion of binary and ternary U alloys was studied in water at 500 and 600 deg F. Alloys contaiiifng less than 40 wt, % Zr additions completely oxidized upon short exposure at 600 deg F, whereas 50 plus wt.% alloys exhibited relatively low corrosion rates. Alloys were sensitive to heat treatment and were most resistant in the quenched condition. The corrosion rates of Zr alloys were linear to slightly accelerated with respect to time. Alloys containing 40, 50, and 60 wt.% Zr were resistant to water at 500 deg F. Molybdenum additions (arc-melted alloys) in the range of 10 to 15 wt.% improved the resistance of U to 600 deg F water but did not result in corrosion-resistant alloys, probably because of inhomogeneity of the alloys studied. The addition of Mo, Nb, Th, Sn, and Ti to uranium--20 wt.% zirconium resulted in several promising alloys: uranium--20 zirconium--5 molybdenum and uranium--20 zirconium-10 niobium. Additions of up to 5 wt, % Mo did not improve the resistance of 40 and 50% Zr alloys to 600 deg F water. A uranium--30 zirconium--5.6 tantalum alloy also exhibited promising resistance to 600 deg F water. Other additions (2 and 5 at.%) which did not improve the resistance of uranium--30 wt.% zirconium were: Sb, Bi, Cc, Cr, Co, Fe, Pb, Ni, Nb, Si, Th, Ti, and W. (auth).

TID.

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ISBN 13 :
Total Pages : 252 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis TID. by :

Download or read book TID. written by and published by . This book was released on 19?? with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:

High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys

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Total Pages : 28 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys by : Stanley Kass

Download or read book High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys written by Stanley Kass and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Roll Cladding Uranium-zirconium and Uranium-zirconium-niobium Alloys with Zircaloy-2 for Plate-type Fuel Elements

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Total Pages : 294 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis Roll Cladding Uranium-zirconium and Uranium-zirconium-niobium Alloys with Zircaloy-2 for Plate-type Fuel Elements by : C. H. Bean

Download or read book Roll Cladding Uranium-zirconium and Uranium-zirconium-niobium Alloys with Zircaloy-2 for Plate-type Fuel Elements written by C. H. Bean and published by . This book was released on 1958 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Roll-clad plate-type fuel elements were developed for use in the Experimental Boiling Water reactor at Argonne National Laboratory. These plates consisted of an uranium-5 wt.% zirconium-1.5 wt.% niobium alloy core clad with Zircaloy-2.

List

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Total Pages : 564 pages
Book Rating : 4.3/5 ( download)

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Book Synopsis List by :

Download or read book List written by and published by . This book was released on 1948 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Proceedings of the Metallurgy Information Meeting Held at Oak Ridge, April 11-13, 1955: Sessions VII through XII, pages 534 through 987

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Total Pages : 374 pages
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Book Synopsis Proceedings of the Metallurgy Information Meeting Held at Oak Ridge, April 11-13, 1955: Sessions VII through XII, pages 534 through 987 by :

Download or read book Proceedings of the Metallurgy Information Meeting Held at Oak Ridge, April 11-13, 1955: Sessions VII through XII, pages 534 through 987 written by and published by . This book was released on 1960 with total page 374 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Power Reactor Technology

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ISBN 13 :
Total Pages : 582 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Power Reactor Technology by :

Download or read book Power Reactor Technology written by and published by . This book was released on 1957 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Zirconium

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Total Pages : 62 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Zirconium by :

Download or read book Zirconium written by and published by . This book was released on 1956 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Effects of Irradiation on the EBWR Fuel Alloy Uranium-5 W/o Zirconium-1.5 W/o Niobium

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Total Pages : 50 pages
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Book Synopsis Effects of Irradiation on the EBWR Fuel Alloy Uranium-5 W/o Zirconium-1.5 W/o Niobium by : J. H. Kittel

Download or read book Effects of Irradiation on the EBWR Fuel Alloy Uranium-5 W/o Zirconium-1.5 W/o Niobium written by J. H. Kittel and published by . This book was released on 1960 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiations were made on small specimens of U-5 wt.% Zr-1.5 wt.% Nb alloy with a wide variety of fabrication histories and heat treatments in order to determine the optimum heat treatment for the fuel plates for the Experimental Boiling Water Reactor (EBW). In the time available, a heat treatment could not be found which simultaneously conferred dimensional stability and corrosion resistance to the alloy. The most effective heat treatment for dimensionally stabilizing swaged or round-rolled material was a 24-hr isothermal transformation from the gamma phase at 650 deg C. This heat treatment was subsequently used as a basis for the heat-treatment specifications for the EBWR fuel plates. In later studies on specimens cut from plates it was learned that the alloy could be adequately stabilized against irradiation growth and also made corrosion- resistant by first reducing the plate 12% in thickness by cold rolling followed by a 24-hr isothermal transformation from the gamma phase at 665 deg C, and finally quenching from 800 deg C. Irradiation growth rates of plate specimens were effectively reduced by the presence of metallurgically bonded Zircaloy-2 cladding. Flat-rolled material under irradiation generally increased in length and width and decreased in thickness.