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The Effects Of Irradiation On Uranium Plutonium Fissium Fuel Alloys
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Book Synopsis The Effects of Irradiation on Uranium-plutonium-fissium Fuel Alloys by : J. A. Horak
Download or read book The Effects of Irradiation on Uranium-plutonium-fissium Fuel Alloys written by J. A. Horak and published by . This book was released on 1962 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: A total of 35 specimens of U-Pu-fissium alloy and 2 specimens of U-10 wt% Pu-5 wt% Mo alloy were irradiated as a part of the fuel-alloy development program for fast breeder reactors at Argonne National Laboratory. Total atom burnups ranged from 1.0 to 1.8% at maximum fuel temperatures ranging from 230 to 470 deg C. Emphasis was placed on the EBR-II Core-III reference fuel material, which is an injection-cast, U-20 wt% Pu-10 wt% fissium alloy. It was found that this material begins to swell catastrophically at irradiation temperatures above 370 deg C. The ability of the fuel to resist swelling did not appear to vary appreciably with minor changes in zirconium or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pour-cast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated.
Book Synopsis THE EFFECTS OF IRRADIATION ON URANIUM-PLUTONIUM-FISSIUM FUEL ALLOYS. Final Report on Metallurgy Program 6.5.5 by :
Download or read book THE EFFECTS OF IRRADIATION ON URANIUM-PLUTONIUM-FISSIUM FUEL ALLOYS. Final Report on Metallurgy Program 6.5.5 written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A total of 35 specimens of U-Pu-fissium alloy and 2 specimens of U-10 wt% Pu-5 wt% Mo alloy were irradiated as a part of the fue1-alloy development program for fast breeder reactors at Argonne National Laboratory. Total atom burnups ranged from 1.0 to 1.8% at maximum fuel temperatures ranging from 230 to 470 deg C. Emphasis was placed on the EBR-II Core-III reference fuel material, which is an injection-cast, U-20 wt% Pu-10 wt% fissium alloy. lt was found that this material begins to swell catastrophically at irradiation temperatures above 370 deg C. The ability of the fuel to resist swelling did not appear to vary appreciably with minor changes in Zr or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pourcast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated. (auth).
Book Synopsis Irradiation Effects in Nuclear Fuels by : J. A. L. Robertson
Download or read book Irradiation Effects in Nuclear Fuels written by J. A. L. Robertson and published by New York : Gordon and Breach. This book was released on 1969 with total page 328 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Effect of Nuclear Radiation on Metallic Fuel Materials by : A. A. Bauėr
Download or read book The Effect of Nuclear Radiation on Metallic Fuel Materials written by A. A. Bauėr and published by . This book was released on 1963 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Metallurgy of Nuclear Fuel by : V. S. Yemel'Yanov
Download or read book The Metallurgy of Nuclear Fuel written by V. S. Yemel'Yanov and published by Elsevier. This book was released on 2013-10-22 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Metallurgy of Nuclear Fuel: Properties and Principles of the Technology of Uranium, Thorium and Plutonium is a systematic analysis of the metallurgy of nuclear fuel, with emphasis on the physical, mechanical, and chemical properties as well as the technology of uranium, thorium, and plutonium, together with their alloys and compounds. The minerals and raw material sources of nuclear fuel are discussed, along with the principles of the technology of the raw material processing and the production of the principal compounds, and of the pure metals and alloys. Comprised of three parts, this volume begins with an introduction to the history of the discovery of uranium and its position in the periodic system; its use as a nuclear fuel; radioactivity and isotopic composition; alloys and compounds; and physical, mechanical, and chemical properties. The effect of mechanical and thermal treatment, thermal cycling and irradiation on the physicochemical properties of uranium is also examined. The next two sections are devoted to thorium and plutonium and includes chapters dealing with their uses, alloys and compounds, and methods of recovery and purification. This book is written for university students, but should also prove useful to young production engineers and scientific workers who are concerned with problems in the metallurgy of nuclear fuel.
Book Synopsis Symposium on Effects of Irradiation on Fuel and Fuel Elements by : W. D. Manly
Download or read book Symposium on Effects of Irradiation on Fuel and Fuel Elements written by W. D. Manly and published by . This book was released on 1959 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Swelling of Uranium and Uranium Alloys by : Gordon G. Bentle
Download or read book Irradiation Swelling of Uranium and Uranium Alloys written by Gordon G. Bentle and published by . This book was released on 1961 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Reactor Fuel Elements by : Albert R. Kaufmann
Download or read book Nuclear Reactor Fuel Elements written by Albert R. Kaufmann and published by . This book was released on 1962 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Effects of Irradiation on the Tensile Properties of Uranium by : R. E. Hueschen
Download or read book The Effects of Irradiation on the Tensile Properties of Uranium written by R. E. Hueschen and published by . This book was released on 1955 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Effects of Irradiation on Some Binary Alloys of Thorium-plutonium and Zirconium-plutonium by : J. A. Horak
Download or read book The Effects of Irradiation on Some Binary Alloys of Thorium-plutonium and Zirconium-plutonium written by J. A. Horak and published by . This book was released on 1962 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium alloy specimens all showed extremely poor dimensional stability, with anisotropic elongations ranging from approximately 100 to 500%. The irradiation growth coefficients for these specimens ranged from 90 to 210 microinches per inch per atom per cent burnup. The poor dimensional stability of the zirconium-plutonium alloy specimens is attributed to a highly preferred grain orientation that presumably developed during cold rolling.
Book Synopsis EFFECTS OF IRRADIATION OF SOME URANIUM-PLUTONIUM ALLOYS. Final Report-- Metallurgy Program 6.5.3 Work Completed by :
Download or read book EFFECTS OF IRRADIATION OF SOME URANIUM-PLUTONIUM ALLOYS. Final Report-- Metallurgy Program 6.5.3 Work Completed written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiations were made on a number of uranium-plutonium alloy specimens made from both cast and extruded materials. The cast alloys included alloys of uranium with 3.7, 5.6, and 13.0 wt. % plutonium, and the extruded alloys included alloys of uranium with 9.5, 14.1, and 15.7 wt.% plutonium. One-half of the extruded specimens were given a heat treatment consisting of heating to 545 deg C and cooling to and holding at 500 deg C for one hour in an attempt to remove the preferred orientation that was anticipated from extrusion. The specimens were irradiated to burnups ranging up to 0.54 at. % with central temperatures ranging up to 490 deg C. The cast specimens were all found to have developed severe surface roughening as a result of the irradiation they received, presumably because of excessively large grain sizes present before irradiation. Identically fabricated unalloyed uranium specimens showed similar behavior. The as-extruded alloy specimens maintained good surface smoothness under irradiation, but showed elongations which were dependent on plutonium content. For example, in samples with 0.4 at.% burnup, a 14.1 wt.% plutonium alloy specimen elongated 96%, whereas an 18.7 wt. % plutonium alloy specimen elongated only 5.4%. The heat-treated extruded specimens did not elongate anisotropically, indicating that the heat treatment used was effective in randomizing the grain orientation. However, the heat-treated specimens developed excessive surface roughening, apparently because the heat treatment caused an undesirably large grain size. (auth).
Book Synopsis Irradiation of U-Mo Base Alloys by : M. P. Johnson
Download or read book Irradiation of U-Mo Base Alloys written by M. P. Johnson and published by . This book was released on 1964 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
Book Synopsis Effects of Irradiation on Some Uranium-plutonium Alloys by : J. H. Kittel
Download or read book Effects of Irradiation on Some Uranium-plutonium Alloys written by J. H. Kittel and published by . This book was released on 1958 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiations were made on a number of uranium-plutonium alloy specimens made from both cast and extruded materials.
Book Synopsis Irradiation of Uranium-fissium Alloys and Related Compositions by : K. F. Smith
Download or read book Irradiation of Uranium-fissium Alloys and Related Compositions written by K. F. Smith and published by . This book was released on 1957 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Self-sustaining Plutonium Recycle in Sodium Graphite Reactors by : T. J. Connolly
Download or read book Self-sustaining Plutonium Recycle in Sodium Graphite Reactors written by T. J. Connolly and published by . This book was released on 1959 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis IRRADIATION OF URANIUM-FISSIUM ALLOYS AND RELATED COMPOSITIONS. Work Performed by :
Download or read book IRRADIATION OF URANIUM-FISSIUM ALLOYS AND RELATED COMPOSITIONS. Work Performed written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation results in the range near 1/2% burnup and 500 to 600 deg C are presented for U-fissium amd U-Mo alloys. Under these conditions both classes of alloys show quite low growth coefficients and volume increases, with a few exceptions. Water queaching either alloy from 850 deg C is shown to be unsatisfactory. The effect of an axial hole for relief of fission gases appears to be inconclusive. Surface condition of irradiated U-base alloys appears to be not quite as good as that for U-20 wt.% Pu base alloys. (auth).
