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Calorimetric power calibration and source effects in the Kansas State University Triga Mark II nuclear reactorHeckman, Edward Albert January 2010 (has links)
Digitized by Kansas Correctional Industries
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Catalytic fixed bed membrane reactor operation for hydrocarbon conversion processesAlthenayan, Faisal M., School of Chemical Engineering & Industrial Chemistry, UNSW January 2006 (has links)
Dry/CO2 reforming is one the hydrocarbon processes that recently has been interesting due to it is ability of producing a lower synthesis gas ratio (H2/CO). This synthesis gas is a highly significant product since it costs more than 50% of the total capital cost of gas to liquid (GTL) process. However, since this reaction is thermodynamically limited, higher temperature or lower pressure is required to achieve higher conversion. Typically, reaction temperatures between 1073 and 1173 K are used for catalytic dry reforming reactions. Consequently, these extreme temperatures lead to a severe carbon deposition causing a catalyst deactivation which is the major difficulty related to CO2 reforming reaction. This has pushed the efforts to be focused mainly on the development of new catalysts. In fact, dry reforming of propane is an equilibrium-limited reaction which can be shifted to the product side by removing one of the products out of the system which can be achieved using a selective membrane reactor. This research is dedicated to investigate and study the catalytic performance of dry reforming of propane over cobalt-nickel catalyst under the temperature range of 773-973 K. This bimetallic catalyst supported on ??-Al2O3 has been utilized in this research since it exhibits better activity, selectivity, and deactivation resistance than monometallic catalysts. Based on this, the primary aims of this thesis are to examine this catalyst and to study the impact of using membrane reactor. In addition, the reaction mechanism and kinetic are investigated using a fixed-bed reactor. Experimental observations have exposed that the catalyst is offering good results under this reaction. The catalysts analysis has confirmed the presence of metal oxides in the catalyst. However, only at a lower carbon dioxide to propane ratio, i.e. lower than 3.5, a carbon signal has been reported. The activation energy study indicates that the process is unlimited by diffusion. The reaction order for propane and carbon dioxide has been found to be zero and 1.17 respectively. This in turn has indicated that C3H8 activation reaction is taking place rapidly and carbon dioxide is suggested to be involved in the rate determining step. In membrane reactor operation, the production rates for H2 and CO have been reported to increase as the sweep gas flow rate increases. The co-current mode offers higher production rate and more stability than counter-current mode over the range of feed ratio. On the other hand, fixed bed reactor shows stable performance and produces more CO and H2 for both modes.
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Chemical analysis for boron in nuclear reactor coolant water /McDaniel, Dawn Marie. January 1983 (has links)
Thesis (M.S.)--Oregon State University, 1984. / Typescript (photocopy). Includes bibliographical references (leaves 125-127). Also available on the World Wide Web.
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Calculation of the reactivity change from voiding the heavy water coolant of the plutonium recycle test reactor /Maryott, James Lee. January 1970 (has links)
Thesis (M.S.)--Oregon State University, 1970. / Typescript (photocopy). Includes bibliographical references (leaves 37-38).
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Modeling the Oregon State University TRIGA reactor using the Attila three-dimensional deterministic transport code /Keller, S. Todd. January 1900 (has links)
Thesis (M.S.)--Oregon State University, 2007. / Printout. Includes bibliographical references (leaves 85-88). Also available on the World Wide Web.
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Deep fueling of large tokamaks by field-reversed configuration injection /Grossnickle, James A. January 2001 (has links)
Thesis (Ph. D.)--University of Washington, 2001. / Vita. Includes bibliographical references (leaves 139-141).
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Complex problems arising in the collision probability theory for neutron transportMatavosian, Robert 29 August 2008 (has links)
Several comprehensive but time consuming neutronic codes are available for performing nuclear reactor and fuel cycle evaluations. In addition, simple models utilizing collision probability theory are used to perform similar tasks with reasonable accuracy. However, the current collision probability theory treats the heterogeneous reactor configurations with a two region unit cell model. This model does not address several important reactor parameters including spatial self-shielding effects and simultaneous use of different reactor fuels within a reactor core. This dissertation studies the fidelity of expanding the collision probability theory to address the stated shortcomings through analyzing two problems. Problem 1 analyzes the effects of self-shielding. The cylindrical fuel region is divided into several sub-regions and an overall equivalent escape probability from the entire fuel region is developed based on the identified neutron transmission and escape probabilities within each fuel sub-region. The multiplication factor and radioisotopic inventory results based on modified V:BUDS (Visualize: Burnup, Depletion, Spectrum) code are in good agreement with benchmark scenarios for a reactor unit cell. The accurate multiplication factor calculation allows more accurate studies on the maximum fuel burnup and radionuclide inventories of interest in nuclear non-proliferation studies. Problem 2 analyzes the effects of simultaneous use of different fuels within a fuel lattice where the zero neutron leakage assumption across the unit cell boundaries is not valid. The developed methodology expands capabilities of the collision probability theory to a supercell model that allows existence of two different fuels. The radioisotopic inventory results for different fuels obtained from the modified V:BUDS code are in excellent agreement with the benchmark problems. These accurate results may be used in general fuel cycle and transmutation studies within power reactors.
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DETERMINATION OF DOMAINS OF NUCLEAR REACTOR STABILITY BY MEANS OF POPOV'S THEOREMCurtis, Robert Thornton, 1923- January 1971 (has links)
No description available.
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THERMAL NEUTRONS IN DUCTED SHIELDSChannon, Frederick Robert, 1938- January 1966 (has links)
No description available.
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ANALYTICAL AND EXPERIMENTAL STUDIES RELATING TO THE SIMULATED START-UP OFIN-CORE THERMIONIC REACTOR SYSTEMSGuppy, James G., 1943- January 1970 (has links)
No description available.
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