Global ETD Search

51	Complex problems arising in the collision probability theory for neutron transport Matavosian, 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. Nuclear reactors Nuclear fuels
52	DETERMINATION OF DOMAINS OF NUCLEAR REACTOR STABILITY BY MEANS OF POPOV'S THEOREM Curtis, Robert Thornton, 1923- January 1971 (has links) No description available. Nuclear reactors -- Mathematical models.
53	THERMAL NEUTRONS IN DUCTED SHIELDS Channon, Frederick Robert, 1938- January 1966 (has links) No description available. Shielding (Radiation) Nuclear reactors.
54	NUMERICAL INTEGRATION OF DYNAMIC NUCLEAR SYSTEMS EQUATIONS BY OPTIMUM INTEGRATING FACTORS Secker, Phillip Allen, 1940- January 1969 (has links) No description available. Nuclear reactors -- Mathematical models.
55	Stability bounds for reactor systems with two feedback mechanisms Lewis, Christopher Henry, 1947- January 1970 (has links) No description available. Nuclear reactors -- Control.
56	Analogue computer studies in nonlinear reactor dynamics Meenan, Peter Michael, 1942- January 1966 (has links) No description available. Nuclear reactors -- Mathematical models.
57	Prompt neutron lifetime from time dependent thermal diffusion equation Hlaing, Shwe, 1936- January 1962 (has links) No description available. Neutrons. Nuclear reactors.
58	Adaptation of the multigroup reactor equations for the University of Arizona's Triga reactor to the IBM-650 computer Gibney, Louis Garland, 1926- January 1961 (has links) No description available. Computer programming. Nuclear reactors.
59	Development of the pre-operational test program for the upgraded nuclear reactor Spear, Richard William, 1942- January 1972 (has links) No description available. Nuclear reactors -- Testing.
60	Numerical solution of the equations for a continuous medium reactor Price, Robert McCollum 08 1900 (has links) No description available. Nuclear reactors Differential equations

Search results