Download or read book Neutron Temperature Measurements in Graphite and in Uranium graphite Reactor written by Garland M. Branch and published by . This book was released on 1946 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An Empirical Prediction of Temperature Gradients in Moderator Graphite Within Operating Nuclear Reactors written by Robert L. Carter and published by . This book was released on 1962 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measuring and Correlating Neutron Exposure and Damage in Graphite written by R. E. Dahl and published by . This book was released on 1963 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Exponential Experiments with Graphite Lattices Containing Multirod Slightly Enriched Uranium Fuel Clusters written by W. W. Brown and published by . This book was released on 1959 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Time of Flight Measurements of Neutron Spectra in a Graphite Uranium Lattice at Different Temperatures written by Atomic Energy Research Establishment (Harwell, England). Nuclear Physics Division and published by . This book was released on 1961 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Exponential Experiments with Graphite moderated Uranium metal Lattices written by R. W. Campbell and published by . This book was released on 1960 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Graphite written by R. E. Nightingale and published by Academic Press. This book was released on 2013-10-02 with total page 566 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Graphite focuses on the development and uses of nuclear graphite, including machining practices, manufacture, nuclear properties and structure, radiation, and electrical resistance. The selection first discusses the applications of graphite in the nuclear industry, machining practices, and manufacture. Discussions focus on early, current, and future applications of graphite, impregnation, graphitization, purification, general machining techniques, and equipment and methods in the nuclear industry. The book then examines the structure and nuclear and properties of graphite. The text evaluates radiation-induced structural and dimensional changes; radiation effects on electrical and thermal properties; and radiation effects on mechanical properties. Topics include radiation effects on crystal structure, electrical resistance, thermoelectric power, magnetoresistance, coefficient of friction, irradiation under stress, and elastic moduli of nuclear graphite. The book also ponders on stored energy, annealing radiation effects, and gas-graphite systems. The selection is a dependable source of data for readers interested in the applications of nuclear graphite.
Download or read book Proceedings of the French American Conference on Graphite Reactors written by and published by . This book was released on 1958 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Age Measurements in Graphite with Gold Resonance Detection written by W. L. Carlson and published by . This book was released on 1950 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Irradiation of Uranium impregnated Graphite at 1500 C to 10 Burnup written by P. J. Peterson and published by . This book was released on 1963 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two type-AUC graphite fuel elements loaded by solution impregnation to an average concentration of 0.115 g/cc of 93.13% enriched U converted to UC and UC2 were irradiated at temperatures of about 1500 deg C to a 10.2% maximum burnup, corresponding to an irradiation level of 219 kwh/cc or 2.45 x 101 fissions/cc of fuel element. Post-irradiation measurements of the elements showed dimensional changes of -4.3 and -4.8% with the grain, and --0.8 to -2.5% across the grain. Weight losses were 3.2 and 5.1% for the individual elements with approximately 11% of the total U being lost from the elements. With-the- grain thermal conductivity at nominal room temperature was reduced by a factor of approximates 7 and electrical conductivities by factors of 3.4 to 8.3, also at room temperature. Impact strength appeared to be somewhat improved by irradiation. Migration of U within the element was detected by radiographic density observations but not evaluated quantitatively. As anticipated, fission product release was high.
Download or read book The Effect of Neutron Irradiation on the Liquid Sodium Dilation of Graphite written by D. L. Henry and published by . This book was released on 1965 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Room Temperature Critical Measurements on Thorium loaded Graphite moderated Oralloy fueled Systems written by G. M. Benson and published by . This book was released on 1962 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Operation of the ORNL Graphite Reactor and the Low intensity Test Reactor 1954 written by A. F. Rupp and published by . This book was released on 1955 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Brookhaven Conference on Neutron Thermalization Experimental aspects of transient and asymptotic phenomena written by Brookhaven National Laboratory and published by . This book was released on 1962 with total page 356 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Graphite written by U.S. Atomic Energy Commission and published by . This book was released on 1962 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt: This compilation contains 958 references to report and published literature. The references pertain primarily to reactor grade graphite, although information on the manufacture and uses of graphite in other fields is included. The references were selected from Nuclear Science Abstracts (NSA), covering the period 1948 through mid-1961. Subject, author, and availability indexes are provided.
Download or read book The Temperature Dependence of Thermal Neutron Diffusion Length in Graphite written by Frederick Faber Touchstone and published by . This book was released on 1970 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Laboratory Course in Reactor Physics Presented in the 1951 1952 Session written by United States. School of Reactor Technology, Oak Ridge, Tenn and published by . This book was released on 1952 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
