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31	Tensoes termicas no vaso de pressao de um reator a agua pressurizada (PWR) BASSEL, WAGEEH S. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:08Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:10:21Z (GMT). No. of bitstreams: 1 00653.pdf: 2722544 bytes, checksum: 26bcce3d962be5c281c69fd5f50fca70 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP pressure vessels thermal stresses water cooled reactors pressurized water reactors
32	Simulacao do modelo termodinamico de pressurizador tipico de PWR em regime transiente por meio do programa CSMP WOISKI, EMANUEL R. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:30:26Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:08Z (GMT). No. of bitstreams: 1 01061.pdf: 1436501 bytes, checksum: 6882eb984f01b285b25a830cd2fc056d (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP analog systems simulators water cooled reactors pressurized water reactors
33	Estudo de acidente de perda de refrigerante por grande ruptura na usina nuclear Angra-1 BORGES, EDUARDO M. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:31:36Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:33Z (GMT). No. of bitstreams: 1 02281.pdf: 4701050 bytes, checksum: 60f7f41ef9b4e9378ba1df67374b6843 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP reactor safety loss of coolant water cooled reactors pressurized water reactors
34	Analise termo-hidraulica e neutronica de reatores a agua pressurizada (PWR) ALVES, CARLOS H. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:30:47Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:12Z (GMT). No. of bitstreams: 1 01358.pdf: 2007506 bytes, checksum: f62b3c2bb7a11dd087227232b25a04d3 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo computer calculations reactor core water cooled reactors pressurized water reactors
35	Tensoes termicas no vaso de pressao de um reator a agua pressurizada (PWR) BASSEL, WAGEEH S. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:08Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:10:21Z (GMT). No. of bitstreams: 1 00653.pdf: 2722544 bytes, checksum: 26bcce3d962be5c281c69fd5f50fca70 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP pressure vessels thermal stresses water cooled reactors pressurized water reactors
36	Optimization of the axial power shape in pressurized water reactors Melik, M. A January 1982 (has links) Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Bibliography: leaves 112-114. / by Mushtaq Ahmad Malik. / M.S. Nuclear Engineering. Pressurized water reactors Nuclear fuel elements Computer programs
37	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
38	Set-theoretic control of a pressurized water nuclear power plant Chenini, Abdelhamid January 1980 (has links) Thesis (Nucl.E)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Abdelhamid Chenini. / Nucl.E Nuclear Engineering. Pressurized water reactors Control Feedback control systems
39	High pressure counterflow CHF. Walkush, Joseph Patrick January 1975 (has links) Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Includes bibliographical references. / This is a report of the experimental results of a program in countercurrent flow critical heat flux. These experiments were performed with Freon 113 at 200 psia in order to model a high pressure water system. An internally heated annulus was used to model a fuel pin in a channel. Only low flowrates were examined. The flow regime was always bubbly or slug, with the liquid primarily on the walls. It was found that critical heat flux of about .9 of the pool boiling value can be expected for up to 20% void. Beyond this, the CHF value decreases uniformly with void. Void fractions up to 70% were investigated, with the results being slightly conservative compared to a similar experiment carried out at atmospheric pressure by Avedisian. / M.S. Nuclear Engineering Pressurized water reactors Nuclear reactor accidents
40	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

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