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31	Aplicacao da tecnica de analise de modos de falha e efeitos ao sistema de resfriamento de emergencia de uma instalacao nuclear experimental / Application of the failure modes and effects analysis technique to the emergency cooling system of an experimental nuclear power plant CONCEICAO JUNIOR, OSMAR 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:16Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:46Z (GMT). No. of bitstreams: 0 / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP failure mode analysis risk assessment eccs pwr type reactors reactor protection systems reactor accidents
32	Simulacao de acidentes de reatividade no reator tipo HTGR Fort Saint Vrain FAINER, GERSON 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:09Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:10:21Z (GMT). No. of bitstreams: 1 01427.pdf: 1451336 bytes, checksum: 8e506680c08097cd2383226d2ea1cc2e (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP accidents reactor accidents analog systems reactor simulators gas cooled reactors htgr type reactors programming b codes
33	An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant De Laquil, Pascal January 1976 (has links) Thesis. 1976. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / by Pascal De Laquil, III. / Ph.D. Nuclear Engineering Fast reactors Breeder reactors Gas cooled reactors Nuclear reactor accidents
34	Decision support systems for nuclear reactor control Anadani, Mohamed January 2000 (has links) No description available. 621.483
35	Estudo de niveis genericos de intervencao para protecao do publico em um acidente nuclear ou emergencia radiologica SUZUKI, FABIO F. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:48:46Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:01Z (GMT). No. of bitstreams: 1 09245.pdf: 3753977 bytes, checksum: f018e58c5c2f31d50af3bf44a9be9821 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP radiation protection administrative procedures reactor accidents radiation accidents emergency plans socio-economic factors Brazil cost comparative evaluations
36	Estudo de niveis genericos de intervencao para protecao do publico em um acidente nuclear ou emergencia radiologica SUZUKI, FABIO F. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:48:46Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:01Z (GMT). No. of bitstreams: 1 09245.pdf: 3753977 bytes, checksum: f018e58c5c2f31d50af3bf44a9be9821 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP radiation protection administrative procedures reactor accidents radiation accidents emergency plans socio-economic factors brazil cost comparative evaluations
37	High pressure condensation heat transfer in the evacuated containment of a small modular reactor Casey, Jason R. 19 December 2012 (has links) At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support of the NuScale Power Inc. (NSP) design certification progress. The facility will be used to simulate design basis accident performance of the reactor's safety systems. The design includes an initially evacuated, high pressure capable containment system simulated by a 5 meter tall pressure vessel. The convection-condensation process that occurs during use of the Emergency Core Cooling System has been characterized during two experimental continuous blowdown events. Experimental data has been used to calculate an average heat transfer coefficient for the containment system. The capability of the containment system has been analytically proven to be a conservative estimate of the full scale reactor system. / Graduation date: 2013 Condensation Nuclear Small Modular Reactor Containment Light water reactors -- Safety measures Nuclear reactors -- Containment Condensation Heat -- Transmission
38	Estudo sobre sistemas de alivio da contencao aplicados a reatores de pequeno porte RIBEIRO, MARIA A.M. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:46:07Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:41Z (GMT). No. of bitstreams: 1 07538.pdf: 15080131 bytes, checksum: 61c8c07c573a7c36c667a13b30f71666 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP PWR type reactors containment filters containment systems pressure release fission product release reactor accidents reactor safety radiation doses radiation protection computer codes
39	Análise do comportamento sob irradiação do combustível nuclear a altas queimas com os programas computacionais FRAPCON e FRAPTRAN / Analysis of the behavior under irradiation of high burnup nuclear fuels with the computer programs FRAPCON and FRAPTRAN REIS, REGIS 10 November 2014 (has links) Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T11:11:38Z No. of bitstreams: 0 / Made available in DSpace on 2014-11-10T11:11:38Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP FUEL ELEMENTS PELLETS BURNUP PWR TYPE REACTORS FUEL RODS COMPUTERIZED SIMULATION F CODES IRRADIATION PROCEDURES ACCURACY REACTIVITY REACTOR ACCIDENTS COMPARATIVE EVALUATIONS
40	Estudo sobre sistemas de alivio da contencao aplicados a reatores de pequeno porte RIBEIRO, MARIA A.M. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:46:07Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:41Z (GMT). No. of bitstreams: 1 07538.pdf: 15080131 bytes, checksum: 61c8c07c573a7c36c667a13b30f71666 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP pwr type reactors containment filters containment systems pressure release fission product release reactor accidents reactor safety radiation doses radiation protection computer codes

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