Validation of a new continuous Monte Carlo burnup code using a Mox fuel assembly-Reference-Cited by-同舟云学术

Validation of a new continuous Monte Carlo burnup code using a Mox fuel assembly

Published:2009-10 Issue:10 Volume:239 Page:1828-1838
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

El bakkari B.,El Bardouni T.,Merroun O.,El Younoussi C.,Boulaich Y.,Boukhal H.,Chakir E.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference8 articles.

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2. Dat, H.T., December 1996. Mise au point de la bibliothèque physique et développement du système PEPABAC (PROGICIEL FAKIR) à l’aide des codes PEPIN et APOLLO1, thèse du doctorat CEA Saclay. Note CEA-N-2815.

3. Hendrichs, Jh.S., Mckinney, Gr.W., November 17, 2007. MCNPX, Version 26E-, LA-UR-07-6632, Los Alamos National Laboratory.

4. MacFarlane, R.E., 2002. NJOY-99 Nuclear Data Processing System [online]. Available: http://t2.lanl.gov/codes/njoy99/index.html (update web site).

5. O’Connor, G.J., Liem, P.H., 2003. Phase IV-B: Results and Analysis of MOX Fuel Depletion Calculations, Nuclear Science NEA/NSC/DOC(2003) 4, OECD 2003.

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