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Irradiation Of Extrusion Clad Uranium 2 W O Zirconium Alloy For Ebr 1 Mark Iii
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Book Synopsis Irradiation of Extrusion-clad Uranium-2 W/o Zirconium Alloy for EBR-1, Mark III by : J. H. Kittel
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.
Download or read book Final Report written by J. W. Weber and published by . This book was released on 1962 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Coextrusion of Zircaloy-clad U-2 W/o Zr Rod for the EBR-I Mark III Core Loading by : H. F. Sawyer
Download or read book Coextrusion of Zircaloy-clad U-2 W/o Zr Rod for the EBR-I Mark III Core Loading written by H. F. Sawyer and published by . This book was released on 1958 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fabrication of Zircaloy-2 Clad Thorium-uranium Alloy Fuel Elements by :
Download or read book Fabrication of Zircaloy-2 Clad Thorium-uranium Alloy Fuel Elements written by and published by . This book was released on 1964 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Book Synopsis Development and Properties of Coextruded Zircaloy-clad Uranium Fuel Elements with Integral End Seals by : H. F. Sawyer
Download or read book Development and Properties of Coextruded Zircaloy-clad Uranium Fuel Elements with Integral End Seals written by H. F. Sawyer and published by . This book was released on 1958 with total page 82 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 development, fabrication and irradiation of extrusion clad uranium rods for NRX. by : J. S. Nelles
Download or read book The development, fabrication and irradiation of extrusion clad uranium rods for NRX. written by J. S. Nelles and published by . This book was released on 1964 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Coextrusion of Zircaloy-Clad U-2 W/o Zr Rod for the Ebr-I Mark III Core Loading by :
Download or read book Coextrusion of Zircaloy-Clad U-2 W/o Zr Rod for the Ebr-I Mark III Core Loading written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Technical data are given concerning the fabrication of Zircaloy-clad U - 2 wt.% Zr alloy rod from extrusion billets. The development of high-yield extrusion billets for fabricating the enriched core and blanket rod is described. (auth).
Book Synopsis The Effects of High-yield Nuclear Explosions by : U.S. Atomic Energy Commission
Download or read book The Effects of High-yield Nuclear Explosions written by U.S. Atomic Energy Commission and published by . This book was released on 1955 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Peaceful Uses of Atomic Energy by : United States. Department of State
Download or read book Peaceful Uses of Atomic Energy written by United States. Department of State and published by . This book was released on 1955 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1960 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Law of Corresponding States for Fused Salts by : H. Reiss
Download or read book Law of Corresponding States for Fused Salts written by H. Reiss and published by . This book was released on 1961 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fast Reactor Database 2006 Update by : International Atomic Energy Agency
Download or read book Fast Reactor Database 2006 Update written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 462 pages. Available in PDF, EPUB and Kindle. Book excerpt: Liquid metal cooled fast reactors (LMFRs) have been under development for about 50 years. The fast reactor database (FRDB) summarised in this report contains detailed design and operational data on 37 fast reactor plants, their thermal power ranging from 10 to 4000 MW, covering experimental, prototype, demonstration and commercial size LMFRs. Data includes physical, hydraulic and thermomechanical characteristics, technological requirements and methods and criteria to ensure safe operation, as well as dimensions, materials information and main design features and performance parameters of reactor cores, components and various systems, along with sketches and drawings.
Book Synopsis Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions by : International Atomic Energy Agency
Download or read book Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions written by International Atomic Energy Agency and published by . This book was released on 2020-07-30 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.
Book Synopsis The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors by : Henri Bailly
Download or read book The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors written by Henri Bailly and published by Lavoisier. This book was released on 1999-01 with total page 642 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text discusses the design, manufacture and behaviour of nuclear fuel in pressurized water reactors (PWR) and fast reactors (FR). It reflects the knowledge of the French Agency for Nuclear Power (CEA) and other specialized companies in the field.
Download or read book Nuclear Weapons Databook written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
