Analysis of the TRAPU irradiation in PHENIX with TRIPOLI-4® and DARWIN-3 for the validation of fast reactor fuel depletion calculations

Author:

Calame Aurélie,Lebrat Jean-François,Buiron Laurent

Funder

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. Archier, P., De Saint Jean, C., Noguère, G., Litaize, O., Leconte, P., Bouret, C. 2014. “OMAC: Nuclear Data Covariances Matrices Library for Reactor Application. PHYSOR 2014, Kyoto, Japan.

2. Americium-241 phase I: reevaluation for JEFF-3.1.1 and a step forward;Bernard;J. Nucl. Sci. Technol.,2012

3. TRIPOLI4®, CEA, EDF and AREVA reference Monte-Carlo code;Brun;Ann. Nucl. Energy,2015

4. Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations;Carrico;J. Nucl. Sci. Eng.,1992

5. Eschbach, R., et al. 2008. Improvement of the Experimental Validation of the DARWIN code system due to the JEFF-3.1 Library for UOX Spent Fuel Inventory and Decay Heat Calculation, Proc. Int. Conf. Physics of Reactors (PHYSOR’08), Interlaken, Switzerland, September 14–19.

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