Download or read book Thermal Expansion of Plutonium Carbides written by P. G. Pallmer and published by . This book was released on 1962 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Review of Thermal Expansion and Density of Uranium and Plutonium Carbides written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The published literature on linear thermal expansion and density of uranium and plutonium carbide nuclear fuels, including UC, PuC, (U, Pu)C, U$sub 2$C3, Pu2C3, and (U, Pu)2C3, is critically reviewed. Recommended values are given in tabular form and additional experimental studies needed for completeness are outlined. 16 tables, 52 references. (auth).

Download or read book The Thermal Expansion of PuC and PuC UC Solid Solution written by Allen E. Ogard and published by . This book was released on 1962 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Thermal Expansion of Plutonium Metal Below 300 K written by Thomas A. Sandenaw and published by . This book was released on 1960 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Thermal Expansion of Plutonium Nitride written by D. F. Carroll and published by . This book was released on 1962 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Materials written by and published by . This book was released on 1967 with total page 320 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 1961 with total page 324 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 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Preparation and Properties of a Plutonium Carbide written by C. P. Johnston and published by . This book was released on 1963 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Out Of Pile Properties of Mixed Uranium Plutonium Carbides Final Report written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fabrication studies to produce high density solid solutions of 80% UC-- 20% PuC, with reproducible structure, composition, and density, were completed. Solid solution (U, Pu)C powder was produced by the oxide-carbon reaction, and the powders were consolidated by cold pressing and sintering. The studies were a continuation of work performed on Contract AT(30-1)-2899 with the USAEC. Two types of material were produced: 1. (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/, single, phase monocarbide pellets with average densities of 12.8 g/cm3 (94% of theoretical), sintered at 1925 deg C; 2. (U/subn 0.95/ at 0.1 wt% Ni sintering aid, major monocarbide phase and minor amount of sesquicarbide phase pellets, with average densities of 13.1 g/cm3 (96.5% of theoretical), sintered at 1550 deg C. The coefficient of thermal expansion was measured as 11.9 x 10−6 / deg C for (U/sub 0.8/Pu/sub 0.2/) x C/sub 0.95/ at 25 to 1400 deg C and 12.3 x 10−6/ deg C for (U/sub 0.8/Pu/sub 0 .2/)C/sub 0.95/ 0.1 wt% Ni at 25 to 1400 deg C. The presence of the nickel sintering aid did not make a significant difference. the values are similar to those of UC, compared at 950 deg C, the maximum temperature to which UC has been measured. The melting point of (U/sub 0.8/ Pu/sub 0.2/)C/sub 0.95/ was found to be 2480 P 20 deg C. The solidus is estimated to be about 2430 deg C. The vapor pressure data in the temperature range of 2100 to 2600 deg K show that the pressure of plutonium is about the same as uranium over (U/sub 0.8/Pu/sub 0.2/C/sub 0.95/. While the uranium data are about an order of magnitude higher than anticipated, based on data for U over UC (probably due to carbon diffusion across the cell), the thermal stability of the fuel in the temperature range of power reactors is still quite good. Thermal conductivity capsules containing (U/sub 0.8/Pu/sub 0.2/) x C/sub 0.95/, (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ plus 0.12 wt% Ni, and UC plus 0.12 wt% Ni (standard) were fabricated. Repairs required by the Mound Laboratory equipment have delayed the measurements. (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ with and without nickel sintering aid, was compatible with type 316 stainless steel, niobium, niobium-- 1% zirconium, 2 1/4 Cr-- 1 Mo steel, and vanadium at 593 deg C and 816 deg C for 1000 and 4000 hr. There was no reaction with Inconel-X after 1000 hr at 593 deg C, but there was a slight reaction after 1000 hr at 816 deg C.A reaction was noted with Zircaloy-2 after 1000 hr at both 593 deg and 816 deg C. The results were similar to those obtained with UC under AEC Contract AT(30-1)-2899. (D.L.C.).

Download or read book The Heat Capacity of Plutonium Metal Below 420 K written by Thomas A. Sandenaw and published by . This book was released on 1960 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Proceedings of the National Topical Meeting on Fast Reactor Systems Materials and Components written by J. F. Weissenberg and published by . This book was released on 1968 with total page 484 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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

Download or read book Equation of State and Transport Properties of Uranium and Plutonium Carbides in the Liquid Region written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: By the use of available low-temperature data for various thermophysical and transport properties for uranium and plutonium carbides, values above the melting point were estimated. Sets of recommended values have been prepared for the compounds UC, PuC, and (U, Pu)C. The properties that have been evaluated are density, heat capacity, enthalpy, vapor pressure, thermal conductivity, viscosity, and emissivity.

Download or read book Power Reactor Technology written by and published by . This book was released on 1959 with total page 770 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1962 with total page 506 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Plutonium Carbides written by A. E. Ogard and published by . This book was released on 1970 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: