skip to main content
Idioma:
Resultados 1 2 3 4 5 next page
Mostrar Somente
Result Number Material Type Add to My Shelf Action Record Details and Options
1
Summary of the Up-to-Date 3-D Nuclear Analyses of ITER Diagnostics Generic Equatorial Port Plug (GEPP) Performed with the Attila Design Code
Summary of the Up-to-Date 3-D Nuclear Analyses of ITER Diagnostics Generic Equatorial Port Plug (GEPP) Performed with the Attila Design Code
Material Type:
Artigo 		Adicionar ao Meu Espaço

Summary of the Up-to-Date 3-D Nuclear Analyses of ITER Diagnostics Generic Equatorial Port Plug (GEPP) Performed with the Attila Design Code

Youssef, Mahmoud Z. ; Feder, Russell

Fusion science and technology, 2013-09, Vol.64 (3), p.571-581 [Periódico revisado por pares]

Taylor & Francis

Texto completo disponível

Citações Citado por
2
Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code
Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code
Material Type:
Artigo 		Adicionar ao Meu Espaço

Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code

Youssef, Mahmoud Z. ; Feder, Russell E.

Fusion engineering and design, 2012-08, Vol.87 (7-8), p.1101-1110 [Periódico revisado por pares]

Elsevier B.V

Texto completo disponível

Citações Citado por
3
3D assessment of nuclear heating, dose rate, and structural damage in the generic ITER diagnostics upper port plugs and adjacent magnet coils
3D assessment of nuclear heating, dose rate, and structural damage in the generic ITER diagnostics upper port plugs and adjacent magnet coils
Material Type:
Artigo 		Adicionar ao Meu Espaço

3D assessment of nuclear heating, dose rate, and structural damage in the generic ITER diagnostics upper port plugs and adjacent magnet coils

Youssef, Mahmoud Z. ; Feder, Russell

Fusion engineering and design, 2010-12, Vol.85 (7), p.1173-1180 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

Texto completo disponível

Citações Citado por
4
Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP “Benchmark CAD Model” with the ATTILA discrete ordinance code
Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP “Benchmark CAD Model” with the ATTILA discrete ordinance code
Material Type:
Artigo 		Adicionar ao Meu Espaço

Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP “Benchmark CAD Model” with the ATTILA discrete ordinance code

Youssef, Mahmoud Z. ; Feder, Russell ; Davis, Ian M.

Fusion engineering and design, 2008-12, Vol.83 (10), p.1661-1668 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

Texto completo disponível

Citações Citado por
5
Neutronics Analysis of the Divertor Interferometer Diagnostics inside the Lower Port #8 Plug of ITER with ATTILA 3-D CAD-Based FEM Code
Neutronics Analysis of the Divertor Interferometer Diagnostics inside the Lower Port #8 Plug of ITER with ATTILA 3-D CAD-Based FEM Code
Material Type:
Artigo 		Adicionar ao Meu Espaço

Neutronics Analysis of the Divertor Interferometer Diagnostics inside the Lower Port #8 Plug of ITER with ATTILA 3-D CAD-Based FEM Code

Youssef, Mahmoud Z. ; Feder, Russell ; Dagher, Mohamed ; Aoyama, Aaron ; Duco, Michael

Fusion science and technology, 2011-08, Vol.60 (2), p.730-737 [Periódico revisado por pares]

Taylor & Francis

Texto completo disponível

Citações Citado por
6
Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER
Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER
Material Type:
Artigo 		Adicionar ao Meu Espaço

Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER

Youssef, Mahmoud Z. ; Ying, Alice

Fusion engineering and design, 2008-12, Vol.83 (10), p.1764-1770 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

Texto completo disponível

Citações Citado por
7
Neutronics assessment of the shielding and breeding requirements for FNSF (standard aspect ratio)
Neutronics assessment of the shielding and breeding requirements for FNSF (standard aspect ratio)
Material Type:
Artigo 		Adicionar ao Meu Espaço

Neutronics assessment of the shielding and breeding requirements for FNSF (standard aspect ratio)

Liu, Haibo ; Abdou, Mohamed A. ; Reed, Robert J. ; Ying, Alice ; Youssef, Mahmoud Z.

Fusion engineering and design, 2010-12, Vol.85 (7), p.1296-1300 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

Texto completo disponível

Citações Citado por
8
Benchmarking the Three-Dimensional CAD-Based Discrete Ordinates Code "ATTILA" Using Integral Dose-Rate Experiments and Comparison to MCNP Results
Benchmarking the Three-Dimensional CAD-Based Discrete Ordinates Code "ATTILA" Using Integral Dose-Rate Experiments and Comparison to MCNP Results
Material Type:
Artigo 		Adicionar ao Meu Espaço

Benchmarking the Three-Dimensional CAD-Based Discrete Ordinates Code "ATTILA" Using Integral Dose-Rate Experiments and Comparison to MCNP Results

Youssef, Mahmoud Z. ; Feder, Russell ; Thompson, Kelly ; Davis, Ian ; Failla, Gregory

Fusion science and technology, 2009-08, Vol.56 (2), p.718-725 [Periódico revisado por pares]

La Grange Park, II: Taylor & Francis

Texto completo disponível

Citações Citado por
9
Optimization of the Integrated Diagnostics in Equatorial Port Plug #3 of ITER for Minimal Interspace Dose Rate
Optimization of the Integrated Diagnostics in Equatorial Port Plug #3 of ITER for Minimal Interspace Dose Rate
Material Type:
Artigo 		Adicionar ao Meu Espaço

Optimization of the Integrated Diagnostics in Equatorial Port Plug #3 of ITER for Minimal Interspace Dose Rate

Youssef, Mahmoud Z. ; Feder, Russell E.

IEEE transactions on plasma science, 2014-05, Vol.42 (5), p.1413-1420 [Periódico revisado por pares]

New York: IEEE

Texto completo disponível

Citações Citado por
10
Analytical formulae for estimating damage rate in the final mirrors of laser inertial fusion energy reactors based on the uncollided neutron flux
Analytical formulae for estimating damage rate in the final mirrors of laser inertial fusion energy reactors based on the uncollided neutron flux
Material Type:
Artigo 		Adicionar ao Meu Espaço

Analytical formulae for estimating damage rate in the final mirrors of laser inertial fusion energy reactors based on the uncollided neutron flux

Youssef, Mahmoud Z ; Kumar, Anil

Fusion engineering and design, 1995-03, Vol.28, p.648-657 [Periódico revisado por pares]

Elsevier B.V

Texto completo disponível

Citações Citado por
Resultados 1 2 3 4 5 next page

Personalize Seus Resultados

  1. Editar

Refine Search Results

Expandir Meus Resultados

  1.   

Mostrar Somente

  1. Recursos Online (39)
  2. Revistas revisadas por pares (37)

Refinar Meus Resultados

Tipo de Recurso 

  1. Artigos  (66)
  2. Anais de Congresso  (4)
  3. Reports  (1)
  4. Mais opções open sub menu

Data de Publicação 

De até
Refinar
  1. Antes de1989  (12)
  2. 1989Até1997  (17)
  3. 1998Até2007  (14)
  4. 2008Até2013  (13)
  5. Após 2013  (16)
  6. Mais opções open sub menu

  • Realização: ABCD-USP USP   Logos de Redes Sociais: Freepik

Buscando em bases de dados remotas. Favor aguardar.