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Publisher : ASTM International
ISBN 13 :
Total Pages : 199 pages
Book Rating : 4./5 ( download)
Download or read book Symposium on Radiation Effects on Materials - Volume 1 written by and published by ASTM International. This book was released on 1958 with total page 199 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Glen William Wensch
Publisher :
ISBN 13 :
Total Pages : 300 pages
Book Rating : 4.3/5 (91 download)
Download or read book Proceedings written by Glen William Wensch and published by . This book was released on 1959 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 294 pages
Book Rating : 4.:/5 (319 download)
Download or read book Proceedings of the 1957 Fast Reactor Information Meeting Held at Chicago, I11., November 20-21, 1957 Sponsored by the Civilian Power Reactor Branch of the Reactor Development Division, UNited States Atomic Energy Commission written by U.S. Atomic Energy Commission and published by . This book was released on 1959 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 296 pages
Book Rating : 4.:/5 (319 download)
Download or read book Proceedings of the 1957 Fast Reactor Information Meeting, Held at Chicago, Ill., November 20-21, 1957 written by U.S. Atomic Energy Commission and published by . This book was released on 1957 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Argonne National Laboratory
Publisher :
ISBN 13 :
Total Pages : 160 pages
Book Rating : 4.3/5 (21 download)
Download or read book Annual Report written by Argonne National Laboratory and published by . This book was released on 1957 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 314 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fuel Elements Conference written by and published by . This book was released on 1959 with total page 314 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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Publisher :
ISBN 13 :
Total Pages : 312 pages
Book Rating : 4.E/5 ( download)
Download or read book TID. written by and published by . This book was released on 19?? with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. G. Jenkins
Publisher :
ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.3/5 (91 download)
Download or read book Diffusion Annealing as a Means of Improving Corrosion Resistance of Zircaloy-2 Clad, Uranium-2 W/o Zirconium Rods written by R. G. Jenkins and published by . This book was released on 1960 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 502 pages
Book Rating : 4.:/5 (37 download)
Download or read book Civilian Power Reactor Program: Addendum. Core parameter studies for selected reactor types written by and published by . This book was released on 1960 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. A. Horak
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Behavior of Restrained and Vented Uranium-2 W/o Zirconium Alloy written by J. A. Horak and published by . This book was released on 1962 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the metallic fuel alloy by at least 200 deg C and also greatly extended the burnup levels to which the fuel could be irradiated.
Author : Albert R. Kaufmann
Publisher :
ISBN 13 :
Total Pages : 760 pages
Book Rating : 4.3/5 (91 download)
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:
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 112 pages
Book Rating : 4.3/5 (243 download)
Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. H. Kittel
Publisher :
ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation of Extrusion-clad Uranium-2 W/o Zirconium Alloy for EBR-1, Mark III written by J. H. Kittel and published by . This book was released on 1959 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: The fuel material specified for the Mark III core of EBR-I was uranium-2 wt. % zirconium alloy coextruded with Zircaloy-2 cladding. From previous work on swaged or rolled uranium-2 wt% zirconium alloy, it was anticipated that the extruded alloy would be dimensionally unstable under irradiation unless stabilized by suitable heat treatment. In order to determine an effective heat treatment, irradiation studies were made on both clad and unclad extruded uranium-2 wt.% zirconium alloy specimens at irradiation temperature estimated at 200 to 750 deg C. The irradiation specimens included material with three different heat treatments, selected on the basis of previous studies, and material transient melted in its cladding. For unclad specimens, it was found that the irradiation temperature strongly influenced the various irradiation growth rates resulting from different heat treatments. Growth rates of the clad specimens were relatively insensitive to either irradiation temperature or prior heat treatment. An exception was the transient-melted material, which shortened under irradiation. The cladding had only limited ability to restrain the swelling rates of specimens irradiated at the more elevated temperatures. Clad transient-melted material was found to be most resistant to high-temperature swelling under irradiation. The results of the present study combined with observations in earlier investigations resulted in a recommendation that the reference heat treatment for the core consist of gamma solution at 800 deg C followed by isothermal transformation at 690 deg C.
Author : J. H. Kittel
Publisher :
ISBN 13 :
Total Pages : 50 pages
Book Rating : 4.3/5 (91 download)
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.
Author :
Publisher :
ISBN 13 :
Total Pages : 730 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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Publisher :
ISBN 13 :
Total Pages : 1330 pages
Book Rating : 4.3/5 (243 download)
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 1330 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Helen C. Friedemann
Publisher :
ISBN 13 :
Total Pages : 76 pages
Book Rating : 4.3/5 (91 download)
Download or read book Bibliography on Uranium Alloys written by Helen C. Friedemann and published by . This book was released on 1959 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
