A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors (English)
- New search for: Pelloni, Sandro
- New search for: Mikityuk, Konstantin
- New search for: Pelloni, Sandro
- New search for: Mikityuk, Konstantin
In:
Annals of Nuclear Energy
;
38
, 1
;
1-13
;
2010
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ISSN:
- Article (Journal) / Electronic Resource
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Title:A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors
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Contributors:Pelloni, Sandro ( author ) / Mikityuk, Konstantin ( author )
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Published in:Annals of Nuclear Energy ; 38, 1 ; 1-13
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2010-08-15
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Size:13 pages
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 38, Issue 1
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
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A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactorsPelloni, Sandro / Mikityuk, Konstantin et al. | 2010
- 14
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Graphite reflecting characteristics and shielding factors for Miniature Neutron Source ReactorsAlbarhoum, M. et al. | 2010
- 21
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Methodologies for optimizing ROP detector layout for CANDU® reactorsKastanya, Doddy / Caxaj, Victor et al. | 2010
- 32
-
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculationsHong, Ser Gi / Kim, Kang-Seog et al. | 2010
- 44
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Calculation and measurement of kinetic parameters of Pakistan Research Reactor-1 (PARR-1)Muhammad, Atta / Iqbal, Masood / Mahmood, Tyyab / Qadir, Javed et al. | 2010
- 49
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Development and application of an extensible engineering simulator for NPP DCS closed-loop testHou, Dong / Lin, Meng / Xu, Zhihong / Yang, Yanhua et al. | 2010
- 56
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A new radiation shielding material: Amethyst oreKorkut, Turgay / Korkut, Hatun / Karabulut, Abdulhalik / Budak, Gökhan et al. | 2010
- 60
-
Vessel coolant mixing effects on a PWR Main Steam Line Break transientZerkak, Omar / Ferroukhi, Hakim et al. | 2010
- 72
-
Approach for the fission fragment total kinetic energy TKE(A) calculation: Application to prompt neutron emission modelsManea, V. / Tudora, A. et al. | 2011
- 72
-
Approach for the fission fragment total kinetic energy TKE(A) calculationManea, V. / Tudora, Anabella et al. | 2010
- 80
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Spectral zone selection methodology for pebble bed reactorsMphahlele, Ramatsemela / Ougouag, Abderrafi M. / Ivanov, Kostadin N. / Gougar, Hans D. et al. | 2010
- 88
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Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTRAlajo, Ayodeji B. / Tsvetkov, Pavel V. et al. | 2010
- 98
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Burning plutonium and minimizing radioactive waste in existing PWRsMittag, S. / Kliem, S. et al. | 2010
- 103
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Azcaxalli: A system based on Ant Colony Optimization algorithms, applied to fuel reloads design in a Boiling Water ReactorEsquivel-Estrada, Jaime / Ortiz-Servin, Juan José / Castillo, José Alejandro / Perusquía, Raúl et al. | 2010
- 112
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GEANT4 simulation of photo-peak efficiency of small high purity germanium detectors for nuclear power plant applicationsRehman, Shakeel Ur / Mirza, Sikander M. / Mirza, Nasir M. / Siddique, Muhammad Tariq et al. | 2010
- 118
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A new procedure to generate resonance integral table with an explicit resonance interference for transport lattice codesKim, Kang-Seog / Hong, Ser Gi et al. | 2010
- 128
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NXcom – A program for calculating attenuation coefficients of fast neutrons and gamma-raysEl-Khayatt, A.M. et al. | 2010
- 133
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Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methodsvan Rooijen, W.F.G. / Chiba, G. et al. | 2010
- 145
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parafish: A parallel FE–P N neutron transport solver based on domain decompositionVan Criekingen, S. / Nataf, F. / Havé, P. et al. | 2010
- 151
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A closed-form solution for the two-dimensional transport equation by the LTS N nodal method in the energy range of Compton effectRodriguez, B.D.A. / Vilhena, M.T. / Hoff, G. / Bodmann, B.E.J. et al. | 2010
- 157
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Determination of AKR-2 leakage beam and verification at iron and water arrangementsKošťál, Michal / Cvachovec, František / Cvachovec, Jiří / Ošmera, Bohumil / Hansen, Wolfgang et al. | 2010
- 166
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Book review. Neutron Physics for Nuclear Reactors, Unpublished Writings of Enrico Fermi, S. Esposito, O. Pisanti (Eds.), World Scientific. 665 p., Price £76.00, ISBN: 9789814291224.Williams, M. M. R. et al. | 2011
- IFC
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Editorial board| 2010