MCART: Solve the Time-Dependent Neutron Transport Equation.
RSICC is authorized to distribute MCART to US Universities Only. All other requests are advised to contact the NEA Data Bank.
Alberto Talamo, Illinois, USA through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.
C-Language; PC Linux (C00809PCX8600).
The MCART code solves, using the method of the characteristics and three different numerical algorithms, the time dependent neutron transport equation, with explicit representation of delayed neutrons, in a bi-dimensional spatial domain for an arbitrary number of energy groups.
10.a) Included Documentation:
“MCART User Manual,” Alberto Talamo (2013).
This package consists of one DVD-ROM with the MCART source code, sample input and output files, and the documentation listed above.
KEYWORDS: DELAYED NEUTRONS, NEUTRON TRANSPORT EQUATION, STEADY-STATE CONDITIONS, TIME-DEPENDENT