Download or read book Critical Studies of Uranium steel and Uranium steel sodium Fast Reactor Cores written by P. I. Amundson and published by . This book was released on 1963 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical studies of two fast reactor cores are described: one contains uranium and steel; the other contains uranium, steel, and sodium. Experimental results are given for fission ratio, central and edge reactivity coefficients, fuel bunching, average prompt neutron lifetime, and distributed worth measurements.
Download or read book Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents ZPR III Assembly 36 written by J. M. Gasidlo and published by . This book was released on 1963 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical studies were performed with a metallic, fast reactor core designed to investigate the effects of replacing highly absorbing U-238 diluent with high-scattering, low-absorbing sodium diluent. The fuel was 15.7 wt.% enriched U-235 and the core contained 18.2 vol.% sodium and 12.68 vol.% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi-alpha, radial fission traverses, and edge reactivity worths of a few samples.
Download or read book Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents APR III Assembly 36 written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi- alpha, radial fission traverses, and edge reactivity worths of a few samples. (auth).
Download or read book Critical Studies of a Dilute Fast Reactor Core written by J. M. Gasidlo and published by . This book was released on 1961 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical studies were performed on a dilute, metallic, fast reactor core. The fuel was 38.6% enriched uranium and reduced-density aluminum was used to simulate sodium coolant. The measured critical mass was 463 kg of U-235 in a 425-liter core. The main part of the experimental program consisted of measurements of the standard fission ratios, a number of central reactivity coefficients, and the prompt neutron lifetime. An additional series of experiments were performed to obtain the worths of aluminum, aluminum oxide, and sodium at various radial positions in the core.
Download or read book Critical Studies of Core B for the Enrico Fermi Atomic Power Plant written by T. A. Doyle and published by . This book was released on 1963 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical studies of a simplified mockup of the second loading (Core B) for the Enrico Fermi fast reactor were made. The core consists of a fully enriched, uranium dioxide-stainless steel cermet clad in stainless steel and cooled by sodium. The high critical mass found for the reactor mockup led to a series of experiments on reducing neutron leakage from the core by surrounding it with different reflectors. With a nickel reflector in place, measurements were made of the reactivity worths of various engineering features of the Fermi reactor, distributed and local reactivity coefficients, various fission and capture rates and fission ratios, and the prompt-neutron lifetime. Finally, with a nickel oxide reflector in place, some of the above measurements were repeated.
Download or read book A Study of Uranium Carbide and Cladding Materials for High temperature Sodium cooled Reactors written by R. D. Hahn and published by . This book was released on 1963 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Doppler Effect Measurements Sodium Void Coefficients and Critical Studies of a 5 000 liter Fast Power Breeder Reactor by the Two zone Method ZPR III Assembly 43 written by J. M. Gasidlo and published by . This book was released on 1964 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Liquid Metal Fast Breeder Reactor written by Thomas B. Cochran and published by Routledge. This book was released on 2015-09-25 with total page 290 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this book, Thomas B. Cochran takes a critical look at the economic and environmental arguments which have been made in favour of an early introduction of the liquid metal fast breeder reactor (LMFBR) as a central component of the United States electrical energy system. First published in 1974, Cochran presents LMFBR as having no environmental advantage over light water reactors and the high temperature gas reactor and seriously questions the economic advantages. This title should be a useful for students interested in environment and sustainability studies, and it is a valuable resource for discussions of future energy strategy.
Download or read book Criticality Studies of Enriched Uranium Metal in UO2 NO3 2 Solutions written by A. Goodwin and published by . This book was released on 1960 with total page 26 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 1973 with total page 1132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Experimental Investigations of Secondary Critical Configurations written by W. Gemmell and published by . This book was released on 1964 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two configurations of a fast reactor core following a postulated accidental meltdown were investigated. The configurations were chosen to represent nonuniform distributions of fuel in which calculations of flux and reactivity worth could be compared with experimental values. The first configuration, Assembly 27, represented a case in which the center of a core had melted, and the top and center portions had collapsed into a dense fuel mass in the bottom of the reactor. The dense region is then surrounded by an annulus with the normal core composition, and this in turn is surrounded by the normal blanket. The second configuration, Assembly 28, represented a core in which vaporizing sodium caused the expulsion of all material from the axis of the core, and the annulus had melted and collapsed into a dense ring of fuel.
Download or read book Nuclear Power Reactor Instrumentation Systems Handbook written by Joseph M. Harrer and published by . This book was released on 1973 with total page 1052 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Empirical Analysis of Critical Mass Data Involving Enriched Uranium Metal in Water written by C. L. Schuske and published by . This book was released on 1962 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Two zone Fast Critical Experiment written by P. I. Amundson and published by . This book was released on 1964 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: This study was conducted to determine what properties of a previously studied dilute power reactor could be duplicated in a smaller two-zone assembly. Reactivity measurements performed included determinations of plate-orientation worth, homogeneity corrections, reactor-segment worths, central reactivity coefficients, and radial worth distributions of axial columns of core materials. Spectral index determinations included: central fission ratios, nuclear track emulsion measurements, fission counter traverses, Rossi-alpha measurements, sodium activation, and natural and enriched uranium foil measurements.
Download or read book Critical Assemblies of Uranium Metal written by R. Gwin and published by . This book was released on 1959 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Uranium in Steel written by Standard Alloys Company and published by . This book was released on 1921 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety and Core Design of Large Liquid metal Cooled Fast Breeder Reactors written by Staffan Alexander Qvist and published by . This book was released on 2013 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt: In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions from human activities, the world is in ever more desperate need of new, inexhaustible, safe and clean primary energy sources. A viable solution to this problem is the widespread adoption of nuclear breeder reactor technology. Innovative breeder reactor concepts using liquid-metal coolants such as sodium or lead will be able to utilize the waste produced by the current light water reactor fuel cycle to power the entire world for several centuries to come. Breed & burn (B & B) type fast reactor cores can unlock the energy potential of readily available fertile material such as depleted uranium without the need for chemical reprocessing. Using B & B technology, nuclear waste generation, uranium mining needs and proliferation concerns can be greatly reduced, and after a transitional period, enrichment facilities may no longer be needed. In this dissertation, new passively operating safety systems for fast reactors cores are presented. New analysis and optimization methods for B & B core design have been developed, along with a comprehensive computer code that couples neutronics, thermal-hydraulics and structural mechanics and enables a completely automated and optimized fast reactor core design process. In addition, an experiment that expands the knowledge-base of corrosion issues of lead-based coolants in nuclear reactors was designed and built. The motivation behind the work presented in this thesis is to help facilitate the widespread adoption of safe and efficient fast reactor technology.
