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Possibilidades teoricas de calculo do programa de computacao HAMMERONUSIC JUNIOR, JOSE 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:24:39Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:02Z (GMT). No. of bitstreams: 1
00030.pdf: 1267034 bytes, checksum: 1e237f210ed3dfb273b208a1ff350b2b (MD5) / Dissertacao (Mestrado) / IPEN/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP
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Possibilidades teoricas de calculo do programa de computacao HAMMERONUSIC JUNIOR, JOSE 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:24:39Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:02Z (GMT). No. of bitstreams: 1
00030.pdf: 1267034 bytes, checksum: 1e237f210ed3dfb273b208a1ff350b2b (MD5) / Dissertacao (Mestrado) / IPEN/D / Escola Politecnica, Universidade de Sao Paulo - POLI/USP
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Nuclear fuel cycle assessment of India: a technical study for U.S.-India cooperationWoddi, Taraknath Venkat Krishna 15 May 2009 (has links)
The recent civil nuclear cooperation proposed by the Bush Administration and
the Government of India has heightened the necessity of assessing India’s nuclear fuel
cycle inclusive of nuclear materials and facilities. This agreement proposes to change the
long-standing U.S. policy of preventing the spread of nuclear weapons by denying
nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have
convinced the world community that India would never relinquish its nuclear arsenal.
This has driven the desire to engage India through civilian nuclear cooperation. The
cornerstone of any civilian nuclear technological support necessitates the separation of
military and civilian facilities. A complete nuclear fuel cycle assessment of India
emphasizes the entwinment of the military and civilian facilities and would aid in
moving forward with the separation plan. To estimate the existing uranium reserves in
India, a complete historical assessment of ore production, conversion, and processing
capabilities was performed using open source information and compared to independent
reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage
nuclear power program entities and all the components of civilian and military
significance were assembled into a flowsheet to allow for a macroscopic vision of the
Indian fuel cycle.
A detailed view of the nuclear fuel cycle opens avenues for technological
collaboration. The fuel cycle that grows from this study exploits domestic thorium
reserves with advanced international technology and optimized for the existing system.
To utilize any appreciable fraction of the world’s supply of thorium, nuclear breeding is
necessary. The two known possibilities for production of more fissionable material in the
reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation
analyzes a thermal breeder core concept involving the CANDU core design. The end-oflife
fuel characteristics evolved from the designed fuel composition is proliferation
resistant and economical in integrating this technology into the Indian nuclear fuel cycle.
Furthermore, it is shown that the separation of the military and civilian components of
the Indian fuel cycle can be facilitated through the implementation of such a system.
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Nuclear fuel cycle assessment of India: a technical study for U.S.-India cooperationWoddi, Taraknath Venkat Krishna 10 October 2008 (has links)
The recent civil nuclear cooperation proposed by the Bush Administration and
the Government of India has heightened the necessity of assessing India's nuclear fuel
cycle inclusive of nuclear materials and facilities. This agreement proposes to change the
long-standing U.S. policy of preventing the spread of nuclear weapons by denying
nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have
convinced the world community that India would never relinquish its nuclear arsenal.
This has driven the desire to engage India through civilian nuclear cooperation. The
cornerstone of any civilian nuclear technological support necessitates the separation of
military and civilian facilities. A complete nuclear fuel cycle assessment of India
emphasizes the entwinment of the military and civilian facilities and would aid in
moving forward with the separation plan. To estimate the existing uranium reserves in
India, a complete historical assessment of ore production, conversion, and processing
capabilities was performed using open source information and compared to independent
reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage
nuclear power program entities and all the components of civilian and military
significance were assembled into a flowsheet to allow for a macroscopic vision of the
Indian fuel cycle.
A detailed view of the nuclear fuel cycle opens avenues for technological
collaboration. The fuel cycle that grows from this study exploits domestic thorium
reserves with advanced international technology and optimized for the existing system.
To utilize any appreciable fraction of the world's supply of thorium, nuclear breeding is
necessary. The two known possibilities for production of more fissionable material in the
reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation
analyzes a thermal breeder core concept involving the CANDU core design. The end-oflife
fuel characteristics evolved from the designed fuel composition is proliferation
resistant and economical in integrating this technology into the Indian nuclear fuel cycle.
Furthermore, it is shown that the separation of the military and civilian components of
the Indian fuel cycle can be facilitated through the implementation of such a system.
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Analise basica e comparacao das caracteristicas do GCFR e LMFBR com o ciclo do torio pela teoria de difusao em grupo de energiaSABUNDJIAN, GAIANE 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:30:25Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:55Z (GMT). No. of bitstreams: 1
01068.pdf: 4318760 bytes, checksum: 8eb4e0a57ec79f8da29124496f7cd8cd (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Diretrizes para avaliação do gasto ambiental no ciclo do combustivel nuclear / Guidelines for evaluation of the environmental expense in the nuclear fuel cycleKOMATSU, CINTIA N. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:55:00Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:16Z (GMT). No. of bitstreams: 0 / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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A Energia nuclear no contexto energetico brasileiro: alternativas de reatores e de ciclos de combustivelANDRADE, GILBERTO G. de 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:41:13Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:32Z (GMT). No. of bitstreams: 1
04724.pdf: 6181985 bytes, checksum: 21b429670816ab7b3ca631d65afc6297 (MD5) / Tese (Doutoramento) / IPEN/T / Universidade Federal do Rio de Janeiro, Rio de Janeiro
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Analise basica e comparacao das caracteristicas do GCFR e LMFBR com o ciclo do torio pela teoria de difusao em grupo de energiaSABUNDJIAN, GAIANE 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:30:25Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:55Z (GMT). No. of bitstreams: 1
01068.pdf: 4318760 bytes, checksum: 8eb4e0a57ec79f8da29124496f7cd8cd (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Diretrizes para avaliação do gasto ambiental no ciclo do combustivel nuclear / Guidelines for evaluation of the environmental expense in the nuclear fuel cycleKOMATSU, CINTIA N. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:55:00Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:16Z (GMT). No. of bitstreams: 0 / Este estudo teve como objetivo estabelecer diretrizes para realização da Contabilidade Ambiental no Ciclo do Combustível Nuclear, tendo como estudo de caso a Unidade de Produção de Hexafluoreto de Urânio do Centro Tecnológico da Marinha em São Paulo. A ciência contábil, em sua vertente Contabilidade Ambiental, fornece um conjunto de ferramentas aptas a mensurar os esforços de proteção, conservação, recuperação e monitoramento do meio ambiente na etapa de Conversão, que vai do concentrado de urânio, o yellow cake, até a fabricação do hexafluoreto de urânio. Foram realizadas pesquisas, visitas, levantamento do banco de dados, entrevistas e consultas ao Relatório Preliminar de Análise de Segurança para se obter o porcentual dos gastos relativos à preservação ambiental que a unidade estudada investiu em relação ao total do gasto do empreendimento. E também foi realizada a valoração da área verde preservada, sendo possível o levantamento do Balanço Ambiental. / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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A Energia nuclear no contexto energetico brasileiro: alternativas de reatores e de ciclos de combustivelANDRADE, GILBERTO G. de 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:41:13Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:32Z (GMT). No. of bitstreams: 1
04724.pdf: 6181985 bytes, checksum: 21b429670816ab7b3ca631d65afc6297 (MD5) / Tese (Doutoramento) / IPEN/T / Universidade Federal do Rio de Janeiro, Rio de Janeiro
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