Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Irradiation Of Uranium Fissium Alloys And Related Compositions Work Performed
Download Irradiation Of Uranium Fissium Alloys And Related Compositions Work Performed full books in PDF, epub, and Kindle. Read online Irradiation Of Uranium Fissium Alloys And Related Compositions Work Performed ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
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).
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 Irradiation Behavior of Uranium-fissium Alloys. EBR-II Project by : J. H. Kittel
Download or read book Irradiation Behavior of Uranium-fissium Alloys. EBR-II Project written by J. H. Kittel and published by . This book was released on 1971 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of uranium-fissium and uranium-fissium-zirconium alloys was irradiated in thermal test reactors to study the relationship of dimensional stability to alloy composition, thermal cycling, burnup, irradiation temperature, post-irradiation heating, and cladding restraint. None of the alloy compositions tested showed irradiation behavior superior to the uranium-5 wt./% fissium alloy that has been used as driver fuel in EBR-II since it began operation. This alloy is among those uranium-base alloys most capable of resisting high-temperature irradiation swelling. None of the alloys showed evidence of the reversion to the metastable gamma phase that has been observed in comparable uranium-molybdenum alloys. Swelling of uranium-fissium alloys was effectively restrained by most of the 0.009-inch thick cladding materials investigated. Local hydrostatic forces due to swelling of the fuel caused the fuel to extrude extensively out of small vent holes in the cladding. Little axial fuel movement occurred within the cladding, however, even when the upper fuel surface was entirely unrestrained.
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.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1550 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation of Uranium-fissium Alloys and Related Compounds by : K. F. Smith
Download or read book Irradiation of Uranium-fissium Alloys and Related Compounds written by K. F. Smith and published by . This book was released on 1957 with total page 55 pages. Available in PDF, EPUB and Kindle. Book excerpt: Surface condition of irradiated uranium-base alloys appears to be not quite as good as that for uranium-20 wt.% plutonium base alloys.
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 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 Irradiation Behavior of Uranium-fissium Alloys. EBR-II Project by : J. H. Kittel
Download or read book Irradiation Behavior of Uranium-fissium Alloys. EBR-II Project written by J. H. Kittel and published by . This book was released on 1971 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of uranium-fissium and uranium-fissium-zirconium alloys was irradiated in thermal test reactors to study the relationship of dimensional stability to alloy composition, thermal cycling, burnup, irradiation temperature, post-irradiation heating, and cladding restraint. None of the alloy compositions tested showed irradiation behavior superior to the uranium-5 wt./% fissium alloy that has been used as driver fuel in EBR-II since it began operation. This alloy is among those uranium-base alloys most capable of resisting high-temperature irradiation swelling. None of the alloys showed evidence of the reversion to the metastable gamma phase that has been observed in comparable uranium-molybdenum alloys. Swelling of uranium-fissium alloys was effectively restrained by most of the 0.009-inch thick cladding materials investigated. Local hydrostatic forces due to swelling of the fuel caused the fuel to extrude extensively out of small vent holes in the cladding. Little axial fuel movement occurred within the cladding, however, even when the upper fuel surface was entirely unrestrained.
Book Synopsis Structures and Properties of Uranium-fissium Alloys by : S. T. Zegler
Download or read book Structures and Properties of Uranium-fissium Alloys written by S. T. Zegler and published by . This book was released on 1961 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study was made of the phase relations and the properties of uranium-fissium alloys which have compositions bracketing that intended for the first core loading of Experimental Breeder Reactor II. The fissium aggregate in the alloys consisted of the elements Zr, Nb, Mo, Ru, Rh, and Pd. Phase relations are shown to parallel closely those in the dominant U--Mo--Ru ternary system. The uranium gamma phase is stabilized down to 552 deg C, while the beta phase is entirely suppressed at high fissium contents. Certain crystallographic data are given and the minor phases that occur in the alloys are identified. In cast and gamma-quenched alloys the retention of the high-temperature gamma phase produced low hardness and low density. The thermal expansion behavior of the alloys is shown to be dependent upon composition and prior thermal history. Thermal conductivity data are presented for uranium and the uranium-fission alloys. The thermal conductivities of the alloys decrease with increasing fissium concentration.
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 Symposium on Radiation Effects on Materials by : American Society for Testing and Materials
Download or read book Symposium on Radiation Effects on Materials written by American Society for Testing and Materials and published by . This book was released on 1957 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Symposium on Radiation Effects on Materials by : American Society for Testing Materials
Download or read book Symposium on Radiation Effects on Materials written by American Society for Testing Materials and published by . This book was released on 1958 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structures and Properties of Uranium-Fissium Alloys. Final Report- Metallurgy Program 4.1.23 by :
Download or read book Structures and Properties of Uranium-Fissium Alloys. Final Report- Metallurgy Program 4.1.23 written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A study was made of the phase relations and the properties of uranium-- fissium alloys which have compositions bracketing that intpnded for the first core loading of Experimental Breeder Reactor II. The fissium aggregate in the alloys consisted of the elements Zr, Nb, Mo, Ru, Rh, and Pd. Phase relations are shown to parallel closely those in the dominant U--Mo--Ru ternary system. The uranium gamma phase is stabilized down to 552 deg C, while the beta phase is entirely suppressed at high fissium contents. Certain crystallographic data are given and the minor phases that occur in the alloys are identified. In cast and gammaquenched alloys the retention of the high-temperature gamma phase produced low hardness and low density. The thermal expsnsion behavior of the alloys is shown to be dependent upon composition and prior thermal history. Thermal conductivity data are presented for uranium and the uranium-- fission alloys. The thermal conductivities of the alloys decrease with increasing fissium concentration. (auth).
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).
Download or read book Reactor Materials written by and published by . This book was released on 1963 with total page 406 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials by :
Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1964 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt:
