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NEA-0236 BOLERO.

BOLERO, 2 Group Burnup for PWR and BWR in R-Z Geometry with Restart and Recycle

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1. NAME OR DESIGNATION OF PROGRAM:  BOLERO.
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2. COMPUTERS
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Program name Package id Status Status date
BOLERO NEA-0236/01 Tested 01-JUL-1970

Machines used:

Package ID Orig. computer Test computer
NEA-0236/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

One or two dimensional (r-z) calculations of burn-up dependent power distribution in a water reactor. Given the geometry and the initial enrichments, the two group flux distribution is calculated, the nuclides are burned for a time step, and again the flux is calculated, and so until a maximum burn-up is accomplished. Recycle and restart options are available. UO2, PUO2 -UO2, THO2 -UO2 fuel are allowed.
The water densities are made consistent, at every instant with the power distribution (via a scheme of outer iterations). Water flow in each channel can also be made consistent with power distributions by imposing that pressure drops be constant throughout the reactor.
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4. METHOD OF SOLUTION

The zero dimensional burn-up programme RIBOT is coupled with a simplified version of the 2-D programme EQUIPOISE and alternately executed. Outer iterations are allowed to recalculate density and/or flow distributions. Control rods are moved to adjust Keff to any desired value.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

50 regions, 2000 mesh points, 50 compositions, 3 control rod banks in each radial region.
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6. TYPICAL RUNNING TIME

On IBM 7094 - .15 sec/(mesh point x time step  x outer iteration). Typically for a BWR, 4 or 5 outer iterations are necessary for convergence. Wide-range of running time is seen from one dimension structures (few minutes for the entire life) to full 2000 points problems (10-20 minutes per time step).
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7. UNUSUAL FEATURES OF THE PROGRAM

Extensive parameters and geo- metrical description are given in input. Spectra, water densities, control rod positions and atom densities are automatically cal- culated. Calculation can be interrupted at any time. Restart options are fully automatic. Reshuffle options are possible (non automatic). Control material (homogenized rods or soluble poison) can be considered fixed or can be moved during burn-up by imposing Keff = constant.
In this case the control material position is calculated as an eigenvalue of the diffusion system.
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8. RELATED AND AUXILIARY PROGRAMS:  EQUIPOISE, RIBOT.
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9. STATUS
Package ID Status date Status
NEA-0236/01 01-JUL-1970 Tested at NEADB
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10. REFERENCES
NEA-0236/01, included references:
- G. Buffoni, P. Loizzo, S. Lopez, M. Petilli:
  Burn-up of Pressurized and Boiling Water Reactors
  CNEN RT/FI(67)28 (1967).
- P. Loizzo:
  The CNEN Code System of Reactor Burn-Up
  Paper to be presented at EAES Symposium on Reactor Fuel Manage
  ment at Risoe (October, 1970).
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11. MACHINE REQUIREMENTS

a) Programme tape.
b) Input output tapes.
c) One scratch tape.
d) Two restart tapes (can be substituted by scratch tapes or discs if the restart option is not used).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0236/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  FORTRAN II monitor.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

         G. Buffoni and S. Lopez
         CNEN Casaccia
         00060 - S. Maria di Galeria
         Italy
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16. MATERIAL AVAILABLE
NEA-0236/01
File name File description Records
NEA0236_01.001 INFORMATION 3
NEA0236_01.002 SOURCE PROGRAMME 4868
NEA0236_01.003 INPUT DATA FOR SAMPLE CASE 1. 146
NEA0236_01.004 INPUT DATA FOR SAMPLE CASE 2. 136
NEA0236_01.005 EDITED LIBRARY 350
NEA0236_01.006 SAMPLE CASE 1 OUTPUT LIST 2859
NEA0236_01.007 SAMPLE CASE 2 OUTPUT LIST 5742
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: BWR reactors, burnup, control elements, one-dimensional, power distribution, pwr reactors, r-z, reprocessing, two-dimensional, two-group.