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41	The effect of axial power shaping on ore utilization in pressurized water reactors Kamal, Altamash January 1980 (has links) Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography: leaves 160-162. / by Altamash Kamal. / M.S. Nuclear Engineering. Pressurized water reactors
42	An evaluation of the fast-mixed spectrum reactor Loh, Wee Tee January 1980 (has links) Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography: leaves 145-147. / by Wee Tee Loh. / M.S. Nuclear Engineering. Fast reactors Breeder reactors Nuclear fuel elements
43	Resonance region neutronics of unit cells in fast and thermal reactors. Salehi, Ali Akbar January 1977 (has links) Thesis. 1977. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography : leaves 226-229. / Ph.D. Nuclear Engineering Nuclear fuel elements Fast reactors Neutron cross sections
44	Experimental investigation of heat transfer characteristics of MITR-II fuel plates, in-channel thermocouple response and calibration. Szymczak, William Joseph January 1976 (has links) Thesis. 1976. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / M.S. Nuclear Engineering Nuclear fuel elements Nuclear reactors Cooling Heat Transmission
45	Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors. Jenks, Timothy Storrs January 1978 (has links) Thesis. 1978. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography: leaves 176-178. / M.S. Nuclear Engineering Pebble bed reactors Nuclear fuel elements Thorium
46	Thermal/hydraulic analysis methods for PWR's Moreno Palacios, Pablo January 1976 (has links) Thesis. 1976. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / by Pablo Moreno. / Nucl.E. Nuclear Engineering Pressurized water reactors Nuclear fuel elements Thermal properties
47	Technology assessment of fusion systems Chang, Franklin Ramón January 1977 (has links) Thesis. 1977. Sc.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Franklin R. Chang. / Sc.D. Nuclear Engineering Fusion reactors Solenoids Nuclear fuel elements
48	A review of the MITR-II basis accident McCauley, John Jay January 1982 (has links) Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by John Jay McCauley. / B.S. Nuclear Engineering. Nuclear reactor accidents Nuclear fuel elements
49	Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada / Modeling of PWR fuel at extended burnup FRAPCON DIAS, RAPHAEL M. 26 August 2016 (has links) Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-08-26T12:33:02Z No. of bitstreams: 0 / Made available in DSpace on 2016-08-26T12:33:02Z (GMT). No. of bitstreams: 0 / Este trabalho tem como objetivo estudar as modificações introduzidas, ao longo de sucessivas versões, nos modelos empíricos do programa computacional FRAPCON utilizado para a simulação do comportamento sob irradiação de varetas combustíveis de Reatores a Água Leve Pressurizada (Pressurized Water Reactor - PWR) em regime de estado estacionário e sob condições de alta queima. No estudo, foram analisados os modelos empíricos utilizados pelo FRAPCON e que são apresentados em sua documentação oficial. Um estudo bibliográfico foi conduzido sobre os efeitos da alta queima em combustíveis nucleares visando melhorar o entendimento dos modelos utilizados pelo FRAPCON nestas condições. Foram feitas simulações do comportamento sob irradiação de uma vareta combustível típica de um reator PWR utilizando as versões 3.3, 3.4 e 3.5 do FRAPCON. Os resultados apresentados pelas diferentes versões do programa foram comparados entre si de forma a verificar as consequências das mudanças de modelo nos parâmetros de saída do programa. Foi possível observar que as modificações introduzidas trouxeram diferenças significativas nos resultados de parâmetros térmicos e mecânicos da vareta combustível, principalmente quando se evoluiu da versão FRAPCON-3.3 para a versão FRAPCON-3.5. Nessa ultima versão, obteve-se menores temperaturas na vareta combustível, menores tensões e deformações no revestimento, menor espessura da camada de oxido formada no revestimento a altas queimas na vareta combustível. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP fuel elements fuel management spent fuel elements burnup reactor fueling pwr type reactors performance feasibility studies computer codes f codes
50	Comparison of conservative and best estimate heat transfer packages with COBRA-IV-I. Massoud, Mahmoud January 1978 (has links) Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICOFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Nucl.E. Nuclear Engineering Nuclear fuel elements Computer programs Pressurized water reactors Nuclear fuel elements Thermal properties Heat Transmission

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