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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
1

Ermittlung der plutonium .Konzentrationsverteilung in Uran und Plutoniumdioxiden mit hilfe der roentgenographischen analyse / Determination of the distribution of plutonium concentration in uranium- and plutonium dioxide by X-ray analysis

RIELLA, HUMBERTO G. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:38:46Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:02Z (GMT). No. of bitstreams: 1 12890.pdf: 2186659 bytes, checksum: 087fa0b384ece6d4147a0d60df0a8644 (MD5) / Tese (Doutoramento) / IPEN/T / Universitaet Karlsruhe - Fakultaet fuer Maschinenbau
2

Ermittlung der plutonium .Konzentrationsverteilung in Uran und Plutoniumdioxiden mit hilfe der roentgenographischen analyse / Determination of the distribution of plutonium concentration in uranium- and plutonium dioxide by X-ray analysis

RIELLA, HUMBERTO G. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:38:46Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:02Z (GMT). No. of bitstreams: 1 12890.pdf: 2186659 bytes, checksum: 087fa0b384ece6d4147a0d60df0a8644 (MD5) / Tese (Doutoramento) / IPEN/T / Universitaet Karlsruhe - Fakultaet fuer Maschinenbau
3

Analise de experimentos criticos de UO2-PuO2 utilizando os sistemas NJOY/AMPX-II/HAMMER-TECHNION

FERNANDES, MARCO A.R. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:36:20Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:30Z (GMT). No. of bitstreams: 1 03995.pdf: 5942263 bytes, checksum: 59581ec48c0cba56318bd21dd195fa2d (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
4

Analise de experimentos criticos de UO2-PuO2 utilizando os sistemas NJOY/AMPX-II/HAMMER-TECHNION

FERNANDES, MARCO A.R. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:36:20Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:30Z (GMT). No. of bitstreams: 1 03995.pdf: 5942263 bytes, checksum: 59581ec48c0cba56318bd21dd195fa2d (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
5

Evaluation of the Mechanical Behavior of a Metal-Matrix Dispersion Fuel for Plutonium Burning

Van Duyn, Lee B. 25 November 2003 (has links)
Recent nuclear proliferation concerns and disarmament agreements have encouraged the U.S. to decrease the excess amount of weapons-grade and reactor-grade plutonium. Continued use of nuclear power without a permanent solution for waste disposition has also led to the need for a reliable method by which the waste products, specifically plutonium, can be utilized or destroyed. One possible solution to plutonium destruction is achieved by manufacturing it into small microspheres and embedding it within an inert metal matrix, then placing it inside a conventional nuclear reactor. This process would burn some of the plutonium while producing electricity. PuO2Zr dispersion fuel has been proposed for such a purpose. Prior to its use, however, this non-fertile metal matrix dispersion fuel must be shown to be mechanically stable in the reactor environment. The internal mechanical interactions of dispersion fuel were modeled using finite element analysis. The results were used to assess the stability of PuO2Zr dispersion fuel inside a reactor. Several parameters, including fuel particle size, volumetric loading, temperature, and burnup, were varied to determine the maximum amount of plutonium that can be burned while maintaining fuel integrity. Earlier experiments using UO2 stainless steel dispersion fuels were used to validate the model and establish a failure criterion. The validated model was then used to determine the parameter space over which PuO2Zr dispersion fuel can be successfully used. These results show that PuO2Zr dispersion fuel is robust and may offer a reliable method for plutonium disposal in current reactors.

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