Papers

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Multigroup Material Cross-Sections Generation With SCALE 6.2.3 for Deterministic Neutron Transport Calculations: Application to a PWR Fuel Element Analysis

Antonella Labarile (Universitat Politecnica Valencia), Arturo Vivancos (Universitat Politècnica València), Alvaro Bernal (Nuclear Safety Council), Teresa Barrachina (Universitat Politècnica València), Rafael Miró (Universitat Politècnica de València), Gumersindo Verdu (Universitat Politecnica de Valencia)

Best Estimate Schemes in Lattice Calculations for Industrial Cases, With the Help of a New Leakage Synthetic Algorithm

B. Vezzoni (Framatome), S. Santandrea (CEA), L. Graziano (Framatome), I. Zmijarevic (CEA)

A Group-Dependent Equivalent Dancoff Factor Cell Method Applied to AIC Control Rod Calculations

Li Mao (CEA), Igor Zmijarevic (CEA), Richard Sanchez (CEA), Nicolas Gerard Castaing (CEA)

Fuel Assembly Analyses With Resonance Calculation Using Energy Spectrum Expansion Method

Ryoichi Kondo (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Satoshi Takeda (Osaka University), Hiroki Koike (Mitsubishi Heavy Industries), Kazuya Yamaji (Mitsubishi Heavy Industries), Daisuke Sato (Mitsubishi Heavy Industries)


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