Observatorio de I+D+i UPM

Memorias de investigación
Communications at congresses:
Improvements in the Prediction Capability of Codes Used to Design Innovative Reactors
Year:2009
Research Areas
  • Naval engineering
Information
Abstract
In this paper, we assess the capability of codes to predict fuel cycle parameters for conceptual transmutation designs. The sensitivity/uncertainty and the Monte Carlo methodologies implemented in ACAB code will be described and the applicability to different nuclear fields is presented. We have studied the impact of activation cross-section uncertainties on relevant fuel cycle parameters, and the nuclear data requirements are evaluated so that such parameters can meet the assigned design target accuracies. We conclude with recommendations for future nuclear data measurement programs, beyond the specific results obtained with the present nuclear data files and the limited available covariance information.
International
Si
Congress
IAEA TM on Specific Applications of Research Reactors: Provision of Nuclear Data
960
Place
Viena (Austria)
Reviewers
Si
ISBN/ISSN
Start Date
12/10/2009
End Date
16/10/2009
From page
0
To page
0
IAEA-NDC Report
Participants
  • Autor: E. GONZALEZ (CIEMAT)
  • Autor: F. ALVAREZ (CIEMAT)
  • Autor: Oscar Luis Cabellos De Francisco (UPM)
  • Autor: JAVIER SANZ GOZALO (UNED)
  • Autor: Nuria Garcia Herranz (UPM)
Research Group, Departaments and Institutes related
  • Creador: Grupo de Investigación: Fusión Nuclear Inercial y Tecnología de fusión
  • Centro o Instituto I+D+i: Instituto de Fusión Nuclear
  • Grupo de Investigación: Ciencia y Tecnología de sistemas avanzados de fisión nuclear
  • Departamento: Ingeniería Nuclear
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