Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a gas-cooled fast reactor

Annals of Nuclear Energy

Volumn 37, Issue 8, 2010, Pages 1101-1106

  Reyes Ramírez, Ricardo ^a   Martín del Campo, Cecilia ^a   François, Juan Luis ^a   Brun, Emeric ^b   Dumonteil, Eric ^b   Malvagi, Fausto ^b  

^a UNIVERSIDAD NACIONAL AUTÓNOMA DE MÉXICO   (Mexico)

^b CEA SACLAY   (France)

Author keywords

Fuel depletion calculations; Gas cooled Fast Reactor; MCNPX C90; TRIPOLI 4 D

Indexed keywords

CODES (SYMBOLS); FAST REACTORS; FUELS; GASES; IRRADIATION; ISOTOPES; NUCLEAR FUELS; PLUTONIUM; SILICON CARBIDE; URANIUM; URANIUM CARBIDE;

EFFECTIVE CROSS SECTIONS; FIRST-ORDER APPROXIMATIONS; FUEL DEPLETION CALCULATION; GAS COOLED FAST REACTORS; INNOVATIVE NUCLEAR ENERGY SYSTEM; MCNPX-C90; MULTIPLICATION FACTOR; TRIPOLI-4;

GAS COOLED REACTORS;

EID: 78751607154     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.04.002     Document Type: Article

References (10)

1. Fensin, M.L., et al., 2006a. Advances in Monte Carlo Depletion Capabilities for MCNPX. In: The American Nuclear Society's 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad, New Mexico, USA, April 3-6, 2006, LA-UR-06-0629.
2. Fensin, M.L., et al., 2006b. Incorporation of a Predictor-Corrector Methodology and 1-Group Reaction Rate Reporting Scheme for the MCNPX Depletion Capability. Los Alamos National Laboratory Report LA-UR-06-3925, Transactions of the American Nuclear Society, vol. 95. Winter Meeting, Albuquerque, New Mexico, November 12-16, 2006, p. 317.
3. Fensin, M.L., et al., 2008. Monte Carlo Burnup Interactive Tutorial. Los Alamos National Laboratory. American Nuclear Society. 2008 Summer Meeting. Anaheim, CA, June 12, 2008, pp. 17-61.
4. Garnier, J.C., et al., 2006. Contribution to GFR design option selection. In: Proceedings of ICAPP'06, Reno, USA, June 4-8, 2006.
5. Hendricks, J.S., et al., 2008. MCNPX 2.6.0 Extensions. Copyright. Los Alamos National Security, LLC. All rights reserved.
6. Katoh, Y., et al., 2005. Materials Fabricated For Futurix-MI Experiment. Gen IV Nuclear Energy Systems. US Department of Energy, ORNL May.
7. Meyer, M.K., 2004. Report on the Feasibility of GFR Fuel for Minor Actinide Management, Argone National Laboratory, University of Chicago.
8. Petit, O., et al., 2008. TRIPOLI-4 Version 6 User Guide. SERMA/LTSD/RT/09-4742/A CEA Saclay 91191Gif-sur-Yvette Cedex, France.
9. Rademakers, F., Brun, R., 1998. ROOT: An Object-Oriented Data Analysis Framework. A report on a data analysis tool currently being developed at CERN. Linux Journal, Issue # 51.
10. Tsilanizara, A., Lahaye, S., Brun, E., 2009. Etat du solveur Evolution et les premières vérifications, SERMA/LLPR/RT/09-4640/A, CEA Saclay 91191Gif-sur-Yvette Cedex, France.