In the present work a neutronic model for the solution of two-dimensionl steady-state multigroup diffusion problems in nuclear reactor core is developed.The module can produce both direct fluxes as well as adjoint neutron importances.

Neutronic Methods for Core Calculations of the LFR Innovative Reactor

-
2008-12-23

Abstract

In the present work a neutronic model for the solution of two-dimensionl steady-state multigroup diffusion problems in nuclear reactor core is developed.The module can produce both direct fluxes as well as adjoint neutron importances.
Rapporto tecnico;Generation IV reactors
File in questo prodotto:
File Dimensione Formato  
RSE-2009-087 Frontespizio.pdf.pdf

accesso aperto

Licenza: Creative commons
Dimensione 1.47 MB
Formato Adobe PDF
1.47 MB Adobe PDF Visualizza/Apri
XCIRTEN-P9LU-011_rev 0.pdf

accesso aperto

Licenza: Creative commons
Dimensione 1.02 MB
Formato Adobe PDF
1.02 MB Adobe PDF Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7294
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
social impact