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NEA-0237 BURNY.

BURNY, 5 Group BWR and PWR Burnup in X-Y Geometry by Diffusion Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  BURNY.
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2. COMPUTERS
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Program name Package id Status Status date
BURNY-5 NEA-0237/01 Tested 01-DEC-1977

Machines used:

Package ID Orig. computer Test computer
NEA-0237/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

BURNY-5 is a burn-up code which uses diffusion theory in x-y geometry with a maximum of 5 energy groups. For BWR either a single fuel element (with reflective boundary condition /or four fuel elements with reflective or periodical boundary conditions) are in the geometrical description.  In the case of PWR cores BURNY-5 can be used for both the 'fine mesh' method and the 'coarse mesh' method.
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4. METHOD OF SOLUTION

The BURNY-5 code consists of the following routines:
RIBOT which calculates the isotopic evolution and the nuclear constants of each fuel cell type. The correlation method is systematically used.
'STRIFF' routine which calculates by correlation formulae the nuclear constants for the non-fuel regions, considered as a homogeneous mixture of water and structure materials.
'ROCCE' calculates the nuclear constants of Ag-In-Cd control cells by means of correlation formulae based on the results of THOMAS and  FORM codes.
'CRUCOR' routine which calculates the blackness parameter and the equivalent nuclear constants of the treatment in diffusion theory of the B4C control rods.
'EXTERMINATOR' is used as x-y-extended diffusion routine for Keff and power distribution evaluation.
'MEDIA' routine for performing some edit preparation and averages for coarse mesh 3-d codes and for the 'BUBA' code in particular.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The codes have been extensively used to design water reactor cores and fuel elements and should therefore be error free; however some options have never  been checked and could give some trouble. This refers especially to  very big problems (more than 5000 meshes).
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES OF THE PROGRAM

Extensive parameters and the geometrical description are given in input. Spectra cross sections and atom densities are automatically calculated. Control rod regions and/or burnable poisons and/or soluble poison are considered. Restart or reshuffling options are possible (non-automatic).
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8. RELATED AND AUXILIARY PROGRAMS:  EQUIPOISE, RIBOT.
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9. STATUS
Package ID Status date Status
NEA-0237/01 01-DEC-1977 Tested at NEADB
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10. REFERENCES
NEA-0237/01, included references:
- G. Buffoni, S. Lopez, I. Maganzani:
  BURNY : A Two-Dimensional Burn-up Program
  RT/FI(67)8 (January 1967) (in Italian)
- P. Loizzo:
  The System of Burn-up Codes BURNY - Input - Output and Operating
  Instructions
  RT/FI(71)8 (April 1971)
- F. Pistella:
  The CNEN Calculation Method for the Neutronic Design of LWR Cores:
  Reactivity and Power Distributions in x,y Geometry Versus Burn-up
  Part I: The Physical Model of the BURNY-BEVE Code System
  RT/FI(75)14  (1975)
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11. MACHINE REQUIREMENTS:  Three scratch files.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0237/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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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
0060 -S. Maria di Galeria
Italy
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16. MATERIAL AVAILABLE
NEA-0237/01
File name File description Records
NEA0237_01.001 SOURCE PROGRAM-F4-EBCDIC 9578
NEA0237_01.002 OVERLAY CARDS 33
NEA0237_01.003 JCL 17
NEA0237_01.004 SAMPLE PROBLEM INPUT DATA 29
NEA0237_01.005 SAMPLE PROBLEM PRINTED OUTPUT 1737
NEA0237_01.006 DATA LIBRARY (BINARY) 150
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: BWR reactors, burnup, correlation functions, diffusion, isotopes, power distribution, pwr reactors, reprocessing, two-dimensional, x-y.