Download or read book Beryllium reflected Graphite moderated Critical Assemblies written by and published by . This book was released on 1957 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Critical Assemblies of Graphite and Enriched Uranium with Beryllium Reflectors written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Data are given on properties of three sets of cylindrical Be reflected, graphite-mcderated critical assemblies. The first set was primarily to establish characteristics as functions of C/Oy atomic ratio of core with nearly constant reflector thickness. Fission distributions were determined. The second set consisted of three assemblies with fixed core to determine the effect of redistributing reflector from the ends to the cylindrical wall. This series was done to provide the Los Alamos Scientific Laboratory's Theoretical Division checks for two-dimensional diffusion code. Flux distributions in the uniformlyreflected assembly were mapped extensively with bare and Cd-shielded foils of oralloy, Au, and In. The third set was to establish the minimum-volume core at C/Oy ~ 350 that could be made critical with available Be. Experimental critical data converted to equivalent spherical systems are compared with resuIts of S/sub 4/ calculations. (auth).
Download or read book Two Beryllium moderated Critical Assemblies written by E. L. Zimmerman and published by . This book was released on 1958 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Graphite Moderated Graphite Reflected Critical Assemblies written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Graphite-moderated, graphite reflected critical assemblies have been set up in the LASL Honeycomb remotely controlled machine. lnformation has been obtained on the critical masses of systems having C/Oy ratios of 6650 and 4093. A third system at a smaller ratio is planned. The reactivity contribution of channels through the core and reflector was determined. (auth).
Download or read book A GRAPHITE MODERATED CRITICAL ASSEMBLY CA 4 written by and published by . This book was released on 1952 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Criticality written by R. L. Scott and published by . This book was released on 1961 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Physics Constants written by Reactor Physics Constants Center (U.S.) and published by . This book was released on 1963 with total page 880 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book TID written by and published by . This book was released on 1959 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Critical Measurements on Near homogeneous BeO moderated Oralloy fueled Systems written by Fred A. Kloverstrom and published by . This book was released on 1960 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Critical Assemblies of Fissionable Materials written by Carroll B. Mills and published by . This book was released on 1965 with total page 28 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 1975-06 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NASA Technical Note written by and published by . This book was released on 1961 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Benchmark Evaluation of Fuel Effect and Material Worth Measurements for a Beryllium Reflected Space Reactor Mockup written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The critical configuration of the small, compact critical assembly (SCCA) experiments performed at the Oak Ridge Critical Experiments Facility (ORCEF) in 1962-1965 have been evaluated as acceptable benchmark experiments for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. The initial intent of these experiments was to support the design of the Medium Power Reactor Experiment (MPRE) program, whose purpose was to study?power plants for the production of electrical power in space vehicles.? The third configuration in this series of experiments was a beryllium-reflected assembly of stainless-steel-clad, highly enriched uranium (HEU)-O2 fuel mockup of a potassium-cooled space power reactor. Reactivity measurements cadmium ratio spectral measurements and fission rate measurements were measured through the core and top reflector. Fuel effect worth measurements and neutron moderating and absorbing material worths were also measured in the assembly fuel region. The cadmium ratios, fission rate, and worth measurements were evaluated for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. The fuel tube effect and neutron moderating and absorbing material worth measurements are the focus of this paper. Additionally, a measurement of the worth of potassium filling the core region was performed but has not yet been evaluated Pellets of 93.15 wt.% enriched uranium dioxide (UO2) were stacked in 30.48 cm tall stainless steel fuel tubes (0.3 cm tall end caps). Each fuel tube had 26 pellets with a total mass of 295.8 g UO2 per tube. 253 tubes were arranged in 1.506-cm triangular lattice. An additional 7-tube cluster critical configuration was also measured but not used for any physics measurements. The core was surrounded on all side by a beryllium reflector. The fuel effect worths were measured by removing fuel tubes at various radius. An accident scenario was also simulated by moving outward twenty fuel rods from the periphery of the core so they were touching the core tank. The change in the system reactivity when the fuel tube(s) were removed/moved compared with the base configuration was the worth of the fuel tubes or accident scenario. The worth of neutron absorbing and moderating materials was measured by inserting material rods into the core at regular intervals or placing lids at the top of the core tank. Stainless steel 347, tungsten, niobium, polyethylene, graphite, boron carbide, aluminum and cadmium rods and/or lid worths were all measured. The change in the system reactivity when a material was inserted into the core is the worth of the material.
Download or read book Critical Measurements on Intermediate energy Graphite U235 Systems written by J. E. Schwager and published by . This book was released on 1957 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Intermediate Reactors written by Carroll B. Mills and published by . This book was released on 1959 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of Cadmium Ratio and Foil Activation Measurements for a Beryllium Reflected Assembly of U 93 15 O2 Fuel Rods 1 506 cm Triangular Pitch written by and published by . This book was released on 2014 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of small, compact critical assembly (SCCA) experiments were completed from 1962 to 1965 at Oak Ridge National Laboratory's Critical Experiments Facility (ORCEF) in support of the Medium-Power Reactor Experiments (MPRE) program. Initial experiments, performed in November and December of 1962, consisted of a core of un-moderated stainless-steel tubes, each containing 26 UOIdaho National Laboratory (INL), Idaho Falls, ID (United States) fuel pellets, surrounded by a graphite reflector. Measurements were performed to determine critical reflector arrangements, fission-rate distributions, and cadmium ratio distributions. The graphite reflectors were then changed to beryllium reflectors. For the beryllium reflected assemblies, the fuel was in 1.506-cm-triangular and 7-tube clusters leading to two critical configurations. Once the critical configurations had been achieved, various measurements of reactivity, relative axial and radial activation rates of 235U, and cadmium ratios were performed. The cadmium ratio, reactivity, and activation rate measurements, performed on the 1.506-cm-array critical configuration, have been evaluated and are described in this paper.
