last modified: 13-AUG-1985 | catalog | categories | new | search |

NEA-0965 LOLA-SYSTEM.

LOLA-SYSTEM, JEN-UPM PWR Fuel Management System Burnup Code System

top ]
1. NAME OR DESIGNATION OF PROGRAM:  LOLA-SYSTEM.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
LOLA-SYSTEM NEA-0965/01 Tested 13-AUG-1985

Machines used:

Package ID Orig. computer Test computer
NEA-0965/01 CDC CYBER 835 CDC CYBER 740
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

The LOLA-SYSTEM is a part of the JEN-UPM code package for PWR fuel management, scope or design calculations. It is a code package for core burnup calculations using nodal theory based on a FLARE type code. The LOLA-SYSTEM includes four modules: the first one (MELON-3) generates the constants of the K-inf and M**2 correlations to be input into SIMULA-3. It needs the K-inf and M**2 fuel assembly values at different conditions of moderator temperature, Boron concentration,  burnup, etc., which are provided by MARIA fuel assembly calculations.

The main module (SIMULA-3) is the core burnup calculation code in three dimensions and one group of energy. It normally uses a geometrical representation of one node per fuel assembly or per quarter of fuel assembly. It has included a thermal hydraulic feedback on flow and voids and criticality searches on boron concentration and control rods insertion.

The CONCON code makes the calculation of the albedoes, transport factors, K-inf and M**2 correction factors to be input into SIMULA-3. The calculation is made in the XY transversal plane. The CONAXI code is similar to CONCON, but in the axial direction.
top ]
4. METHOD OF SOLUTION

MELON-3 makes a mean squares fit of K-inf and M**2 values at different conditions in order to determine the constants of the feedback correlations.

SIMULA-3 uses a modified one-group nodal theory, with a new transport kernel that provides the same node interface leakages as a fine mesh diffusion calculation.

CONCON and CONAXI determine the transport and correction factors, as well as the albedoes, to be input into SIMULA-3. They are determined by a method of leakages equivalent to the detailed diffusion calculation of CARMEN or VENTURE; these factors also include the heterogeneity effects inside the node.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Number of axial nodes less than or equal 34.
Number of material types less than or equal 30.
Number of fuel assembly types less than or equal 10.
top ]
6. TYPICAL RUNNING TIME

The module with a more relevant running time  is the SIMULA-3, with about 5' cpu time per burnup step in the UNIVAC 1100/80.
NEA-0965/01
NEA-DB executed the test cases of the system on a CDC CYBER 740 computer. The following CPU running times were required for the different modules: 226 seconds (SIMULA-3); 1.7 seconds (MELON-3); 9.9 seconds (CONAXI). The module CONCON was not executed.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM

SIMULA-3 uses as input data the interface units generated by the other modules, with the correlation constants, the transport factors, the albedoes and the K-inf and M**2 correction factors.
top ]
8. RELATED AND AUXILIARY PROGRAMS

MARIA-SYSTEM generates the K-inf and M**2 values at different conditions to be input into MELON-3.

CARMEN-SYSTEM provides the detailed fine-mesh fluxes and the cross sections by zone to be input into CONCON and CONAXI codes.
top ]
9. STATUS
Package ID Status date Status
NEA-0965/01 13-AUG-1985 Tested at NEADB
top ]
10. REFERENCES

- J.M. Aragones, C. Ahnert, "MARIA-SYSTEM, A Code Block for PWR Fuel   Assembly Calculations" JEN-543 (1983).
- C. Ahnert, J.M. Aragones, "CARMEN-SYSTEM, A Code Block for
Neutronic PWR Calculation by Diffusion Theory with Space Dependent    Feedback Effects", JEN-515 (1982).
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
NEA-0965/01, included references:
- J.M. Aragones, C. Ahnert,
  J. Gomez Santamaria and I. Rodriguez Olabarria:
  'LOLA SYSTEM": A Code Block for Nodal PWR Simulation.
  JEN 568  (1984)
top ]
11. MACHINE REQUIREMENTS

35 K words for the code source and about 60 K words for the data.
NEA-0965/01
Main storage requirements for the different modules of  the system are as follows: 163,600 (octal) words (SIMULA-3); 41,600  (octal) words (MELON-3); 210,000 (octal) words (CONCON); 50,000 (octal) words (CONAXI).
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0965/01 FORTRAN-77
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
UNIVAC-1100, EXEC 8
NEA-0965/01
NOS 1.4-531 (CDC CYBER 740).
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

This code has been included in
the Coordinated Research Programme (CRP) on "Codes Adaptable to
Small and Medium-Size Computers Available in Developing Countries
for In-Core Fuel Management" of the International Atomic Energy
Agency.

CDC version:
            J.M. Aragones
            Escuela Tecnica Superior de Ingenieros Industriales
            Jose Gutierrez Abascal 2
            MADRID, Spain

UNIVAC version:
            C. Ahnert
            Junta de Energia Nuclear
            Avenida Complutense
            MADRID, Spain
top ]
16. MATERIAL AVAILABLE
NEA-0965/01
File name File description Records
NEA0965_01.003 INFORMATION FILE 80
NEA0965_01.004 JCL FOR LOLA-SYSTEM 74
NEA0965_01.005 SIMULA-3 SOURCE PROGRAM 3500
NEA0965_01.006 SIMULA-3 TEST PROBLEM INPUT DATA 112
NEA0965_01.007 MELON-3 SOURCE PROGRAM 1160
NEA0965_01.008 MELON-3 TEST PROBLEM INPUT DATA 36
NEA0965_01.009 CONCON SOURCE PROGRAM 856
NEA0965_01.010 CONCON TEST PROBLEM INPUT DATA 9
NEA0965_01.011 CONAXI SOURCE PROGRAM 463
NEA0965_01.012 CONAXI TEST PROBLEM INPUT DATA 136
NEA0965_01.013 MELON-3 PUNCHED OUTPUT(TAPE 8) 51
NEA0965_01.014 CONCON PUNCHED OUTPUT(TAPE 2) 213
NEA0965_01.015 SIMULA-3 PRINTED OUTPUT 693
NEA0965_01.016 MELON-3 PRINTED OUTPUT 474
NEA0965_01.017 CONCON PRINTED OUTPUT 362
NEA0965_01.018 CONAXI PRINTED OUTPUT 316
top ]
17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: fuel management, pwr reactors.