A neutronic program for critical and nonequilibrium study of mobile fuel reactors: The Cinsf1D code

Nuclear Science and Engineering

Volumn 143, Issue 1, 2003, Pages 33-46

  Lecarpentier, David ^a   Carpentier, Vincent ^a  

^a EDF R AND D   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; COOLANTS; CRITICALITY (NUCLEAR FISSION); FINITE DIFFERENCE METHOD; FISSION REACTIONS; LIQUID FUELS; NEUTRONS;

MOBILE FUEL REACTORS; MOLTEN SALT REACTORS;

NUCLEAR REACTORS;

EID: 0037263129     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-A2316     Document Type: Article

References (9)

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9. Press et al., Numerical Recipes in FORTRAN, Cambridge University Press (1992).