RSICC CODE PACKAGE CCC-809

 

1.         NAME AND TITLE

MCART:  Solve the Time-Dependent Neutron Transport Equation.

 

RESTRICTIONS:

RSICC is authorized to distribute MCART to US Universities Only.  All other requests are advised to contact the NEA Data Bank.

 

2.         CONTRIBUTORS

Alberto Talamo, Illinois, USA  through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.

 

3.         CODING LANGUAGE AND COMPUTER

C-Language; PC Linux (C00809PCX8600).

 

4.         NATURE OF PROBLEM SOLVED

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.

 

5.         METHOD OF SOLUTION

MCART uses the method of the characteristics, and three different numerical algorithms are used to solve the time dependent neutron transport equation with explicit representation of the delayed neutrons. The code uses dynamic memory allocation and therefore only the RAM memory limit sets the maximum number of energy groups. The code contains OPENMP4 and OPENGL5 instructions for parallel computing and plotting, respectively.

 

6.         RESTRICTIONS OR LIMITATIONS

None listed.

 

7.         TYPICAL RUNNING TIME

Problem dependent.

 

8.         COMPUTER HARDWARE REQUIREMENTS

PC (Linux).

 

9.         COMPUTER SOFTWARE REQUIREMENTS

MCART contains OPENMP and OPENGL instructions for parallel computing and plotting, respectively.

 

10.       REFERENCES

10.a) Included Documentation:

“MCART User Manual,” Alberto Talamo (2013).

 

11.       CONTENTS OF CODE PACKAGE

This package consists of one DVD-ROM with the MCART source code, sample input and output files, and the documentation listed above.

 

12.       DATE OF ABSTRACT

November 2013.

 

KEYWORDS:      DELAYED NEUTRONS, NEUTRON TRANSPORT EQUATION, STEADY-STATE CONDITIONS, TIME-DEPENDENT