EBookClubs

Read Books & Download eBooks Full Online

EBookClubs

Read Books & Download eBooks Full Online

Book The Irradiation Behavior of ZrO2   UO2

Download or read book The Irradiation Behavior of ZrO2 UO2 written by B. F. Rubin and published by . This book was released on 1962 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Irradiation Behavior of ZrO2 UO2 Fuels

Download or read book The Irradiation Behavior of ZrO2 UO2 Fuels written by B. F. Rubin and published by . This book was released on 1962 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Behavior of Restrained and Vented Uranium 2 W o Zirconium Alloy

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.

Book Irradiation Behavior of Restrained and Vented Uranium 2 W o Zirconium Alloy  Final Report Programs 6 1 22 and 6 1 27

Download or read book Irradiation Behavior of Restrained and Vented Uranium 2 W o Zirconium Alloy Final Report Programs 6 1 22 and 6 1 27 written by and published by . This book was released on 1962 with total page 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. (auth).

Book Irradiation Behavior of Zircaloy 2 Clad Thorium uranium zirconium Fuel Elements

Download or read book Irradiation Behavior of Zircaloy 2 Clad Thorium uranium zirconium Fuel Elements written by J. W. Goffard and published by . This book was released on 1967 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-11 with total page 698 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Bettis Technical Review

Download or read book Bettis Technical Review written by and published by . This book was released on 1963-10 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A Metallographic and X ray Study of the UO2 ZrO2 System

Download or read book A Metallographic and X ray Study of the UO2 ZrO2 System written by I. Cohen and published by . This book was released on 1962 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Behavior of Bulk B4C and B4C SiC Burnable Poison Plates

Download or read book Irradiation Behavior of Bulk B4C and B4C SiC Burnable Poison Plates written by R. G. Gray and published by . This book was released on 1963 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Comprehensive Nuclear Materials

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Book Reactor Materials

Download or read book Reactor Materials written by and published by . This book was released on 1966 with total page 320 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Keywords Index to U S  Government Technical Reports

Download or read book Keywords Index to U S Government Technical Reports written by United States. Dept. of Commerce. Office of Technical Services and published by . This book was released on 1963 with total page 1042 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Atomic Energy Research Reports for Sale by the U S  Department of Commerce  Office of Technical Services

Download or read book Atomic Energy Research Reports for Sale by the U S Department of Commerce Office of Technical Services written by Business and Defense Services Administration and published by . This book was released on 1963 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Ceramic Nuclear Fuels in the System ZrO2   CaO   UO2

Download or read book Ceramic Nuclear Fuels in the System ZrO2 CaO UO2 written by J. H. Handwerk and published by . This book was released on 1962 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: Potential nuclear fuels in the system ZrO2-CaO-UO2 were investigated. Cubic fluorite-type solid solutions, as indicated by x-ray diffraction patterns, were formed by sintering CaO-stabilized ZrO2 and U3O8 compacts in either air or H2. A continuous solid solution was found between urania and stabilized zirconia with H2 sintering at 1750 deg C. Air sintering produced a limited region of solid solution in the stabilized zirconia portion of the system at 1450 deg C. Results on phase identification, oxidation behavior, and water corrosion are presented.

Book Irradiation Performance of Highly Enriched Fuel

Download or read book Irradiation Performance of Highly Enriched Fuel written by C. E. Lacy and published by . This book was released on 1958 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Scientific and Technical Aerospace Reports

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: