Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

[ top ]

[ top ]

To submit a request, click below on the link of the version you wish to order. Rules for end-users are
available here.

Program name | Package id | Status | Status date |
---|---|---|---|

LABAN-PEL | IAEA1232/01 | Tested | 17-FEB-1995 |

Machines used:

Package ID | Orig. computer | Test computer |
---|---|---|

IAEA1232/01 | Many Computers | Many Computers |

[ top ]

3. DESCRIPTION OF PROGRAM OR FUNCTION

LABAN-PEL solves the multigroup neutron diffusion equations in 2-D Cartesian geometry by means of the high-order response matrix eigenvalue method. LABAN-PEL is a modified version of the LABAN code originally written by Lindahl. The new version extends the capabilities of LABAN with regard to the treatment of neutron migration by including an option to utilize full group-to-group diffusion coefficient matrices. In addition, the code has been converted from single to double precision and the necessary routines added to activate its multigroup capability. The code has been shown to be a useful and valuable method for benchmarking coarse-mesh (nodal) reactor calculational methods.

LABAN-PEL solves the multigroup neutron diffusion equations in 2-D Cartesian geometry by means of the high-order response matrix eigenvalue method. LABAN-PEL is a modified version of the LABAN code originally written by Lindahl. The new version extends the capabilities of LABAN with regard to the treatment of neutron migration by including an option to utilize full group-to-group diffusion coefficient matrices. In addition, the code has been converted from single to double precision and the necessary routines added to activate its multigroup capability. The code has been shown to be a useful and valuable method for benchmarking coarse-mesh (nodal) reactor calculational methods.

[ top ]

4. METHOD OF SOLUTION

The solution to the global reactor problem is obtained by coupling the local solutions for many subregions via partial currents. The local solutions are represented by response functions which characterize the response of a particular subregion to a partial current incident anywhere on its surface. In the high-order response matrix method, the spatial shapes of partial currents on nodal (coarse-mesh) interfaces are approximated by Legendre polynomial expansions of arbitrary order. The nodal response matrices (for homogeneous nodes) are generated by solving the local multigroup diffusion equations semi-analytically by means of a Fourier series method. By treating all energy groups simultaneously and including both scattering and fission processes in the local response matrices, an explicit eigenvalue problem is defined. However, the response matrices are implicitly dependent on a reactivity eigenvalue which is iteratively adjusted until the explicit eigenvalue equals unity. The final value of the implicit eigenvalue is then the multiplication factor (keff).

The solution to the global reactor problem is obtained by coupling the local solutions for many subregions via partial currents. The local solutions are represented by response functions which characterize the response of a particular subregion to a partial current incident anywhere on its surface. In the high-order response matrix method, the spatial shapes of partial currents on nodal (coarse-mesh) interfaces are approximated by Legendre polynomial expansions of arbitrary order. The nodal response matrices (for homogeneous nodes) are generated by solving the local multigroup diffusion equations semi-analytically by means of a Fourier series method. By treating all energy groups simultaneously and including both scattering and fission processes in the local response matrices, an explicit eigenvalue problem is defined. However, the response matrices are implicitly dependent on a reactivity eigenvalue which is iteratively adjusted until the explicit eigenvalue equals unity. The final value of the implicit eigenvalue is then the multiplication factor (keff).

[ top ]

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

LABAN-PEL is restricted to the solution of 2-D diffusion problems but, since it is a variably dimensioned code, there are no other restrictions (e.g. on the number of energy groups). The size of the problem is restricted only by the computer core storage available.

LABAN-PEL is restricted to the solution of 2-D diffusion problems but, since it is a variably dimensioned code, there are no other restrictions (e.g. on the number of energy groups). The size of the problem is restricted only by the computer core storage available.

[ top ]

6. TYPICAL RUNNING TIME

The running time for a typical 2-group problem such as the 2-D IAEA Benchmark Problem using a P4 approximation (reference quality solution) is of the order of 4 minutes on a 33MHz i80386 PC with an i80837 mathematics co-processor.

The running time for a typical 2-group problem such as the 2-D IAEA Benchmark Problem using a P4 approximation (reference quality solution) is of the order of 4 minutes on a 33MHz i80386 PC with an i80837 mathematics co-processor.

IAEA1232/01

The package was tested by NEA-DB on both a 66-MHz PC/80486 and a DEC VAX 6000. The following execution times were required to run the two sample problems included in this package:(A) PC/80486: 58 seconds for SAMPLE1; 1min21sec for SAMPLE2.

(B) VAX 6000: 55 seconds for SAMPLE1; 1min16sec for SAMPLE2.

[ top ]

[ top ]

[ top ]

10. REFERENCES

- G.S-O. Lindahl,

Multi-Dimensional Response Matrix Method,

PhD Thesis, Kansas State University (1976)

- S-O. Lindahl and Z. Weiss,

Adv. Nucl. Sci. Techn., 13,

736 (1981)

- G.S-O. Lindahl,

Multi-Dimensional Response Matrix Method,

PhD Thesis, Kansas State University (1976)

- S-O. Lindahl and Z. Weiss,

Adv. Nucl. Sci. Techn., 13,

736 (1981)

IAEA1232/01, included references:

- E.Z. Mueller:LABAN-PEL, A Two-Dimensional, Multigroup Diffusion, High-Order

Response Matrix Code,

PEL-309, Atomic Energy Corporation of South Africa (June 1991).

- E.Z. Mueller and Z.J. Weiss:

Benchmarking with the Multigroup Diffusion High-Order Response

Matrix Method

Reprint Ann. Nucl. Sci. Techn., Vol. 18, No. 9 pp. 535-544 (1991).

[ top ]

IAEA1232/01

The program was installed at NEA-DB on both a DELL 466/L PC/80486 with 66 MHz and 12 MBytes of RAM: and a DEC VAX 6000-510.[ top ]

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: Mainframe: IBM 370 MVS; i80836 PC: UNIX/XENIX, DOS-4.

IAEA1232/01

The installation on the PC was done under MS-DOS v.6.2 and using the FORTRAN compiler Lahey F77L-EM/32 Version 5.20. On the VAX, the operation system was VMS 5.5-2 and the FORTRAN-77 compiler was version 5.5-98.[ top ]

[ top ]

[ top ]

IAEA1232/01

File name | File description | Records |
---|---|---|

IAEA1232_01.001 | Information file | 105 |

IAEA1232_01.002 | Source for LABANPEL | 6634 |

IAEA1232_01.003 | Executable file for LABANPEL -Lahey compiler | 0 |

IAEA1232_01.004 | Input data for sample problem 1 | 59 |

IAEA1232_01.005 | Input data for sample problem 2 | 52 |

IAEA1232_01.006 | Output for sample problem 1 | 265 |

IAEA1232_01.007 | Output for sample problem 2 | 518 |

IAEA1232_01.008 | Input/Output files definition for LABANPEL | 3 |

IAEA1232_01.009 | JCL for mainframe compilation of LABANPEL | 9 |

IAEA1232_01.010 | JCL for mainframe execution of LABANPEL | 8 |

IAEA1232_01.011 | Message errors from Lahey compiler | 0 |

IAEA1232_01.012 | DOS file-names | 11 |

Keywords: diffusion equations, multigroup, response functions, two-dimensional, x-y.