Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation

Annals of Nuclear Energy

Volumn 36, Issue 7, 2009, Pages 878-885

  Leppänen, Jaakko ^a  

^a VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

Author keywords

[No Author keywords available]

Indexed keywords

BURNUP CALCULATION; COMPUTER MEMORIES; CROSS SECTION DATA; GRID SIZE; IRRADIATED MATERIALS; MEMORY USAGE; MONTE CARLO; MONTE CARLO NEUTRON; PRACTICAL METHOD; REACTION CROSS-SECTIONS; REACTOR PHYSICS; REDUNDANT DATA; SPEED-UP;

BOILING WATER REACTORS; FISSION PRODUCTS; ISOTOPES; TRANSPORT PROPERTIES;

MONTE CARLO METHODS;

EID: 67349185584     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2009.03.019     Document Type: Article

References (8)

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3. Leppänen, J., 2009. PSG2/Serpent - A Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code, User's Manual (February 2, 2009). VTT Technical Research Centre of Finland.
4. McFarlane, R.E., Muir, D.W., 1994. NJOY Nuclear Data Processing System. LA-12740-M. Los Alamos National Laboratory.
5. Naito, Y., Okuno, H., 1996. OECD/NE Burnup Credit Criticality Benchmark Phase IIIB. Japan Atomic Energy Research Institute.
6. Poston, D.I., Trellue, H.R., 1999. User's Manual, Version 2.0 for Monteburns, Version 1.0. LA-UR-99-4999. Los Alamos National Laboratory.
7. Woodcock, E.R. et al., 1965. Techniques Used in the Gem Code for Monte Carlo Neutronics Calculations in Reactors and Other Systems of Complex Geometry. ANL-7050. Argonne National Laboratory.
8. X-5 Monte Carlo Team, 2003. MCNP - A General Monte Carlo N-Particle Transport Code, Version 5. LA-CP-03-0245. Los Alamos National Laboratory.