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NEA-0466 SHREDI.

SHREDI, Neutron Flux and Neutron Activation in 2-D Shields by Removal Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  SHREDI.
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2. COMPUTERS
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Program name Package id Status Status date
SHREDI NEA-0466/01 Tested 01-JUL-1976

Machines used:

Package ID Orig. computer Test computer
NEA-0466/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

SHREDI is a removal - diffusion neutron shielding code. The program computes neutron fluxes and activations in bidimensional sections (x,y or r,z) of the shield. It is also possible to consider shielding points with the same y or z coordinate (monodimensional problems).
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4. METHOD OF SOLUTION

The integrals which define the removal fluxes are computed in some shield points by means of a particular algorithm based on the Simpson's and trapezoidal rules. For the diffusion calculation the finite difference method is used. The removal sources are interpolated in all diffusion points by Chebyshev polynomials.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima

  number of removal energy groups NGR = 40
  number of diffusion energy groups NGD = 40
  number of the reactor core and shield materials NCMP = 50
  number of core mesh points in r (or x) direction for integral calculation = 75
  number of core mesh points in z (or y) direction for integral calculation = 75
  number of core mesh points in theta (or z) direction for integral calculation = 75
  number of shield mesh points for the neutron flux calculation in r (or x) direction NPX = 200
  number of shield mesh points for the neutron flux calculation in z (or y) direction NPY = 200
n.b. (NPX * NPY) le 12000.
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6. TYPICAL RUNNING TIME

The problem: 19 removal groups, 26 diffusion groups, removal fluxes calculated at 8 x 36 points using 41 x 3 x 7  core points, diffusion and neutron fluxes calculated at 23 x 161 shield points, 6 activation calculations carried out at the same shield points, takes a total time of 24 minutes, 7 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

The code executes calculations for sufficiently general bidimensional (or monodimensional) shields  of reactors for which the removal - diffusion model is good. Shield  parts may be excluded from the calculation.
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8. RELATED AND AUXILIARY PROGRAMS:  Nuclear data library is prepared by the program SABLIB.
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9. STATUS
Package ID Status date Status
NEA-0466/01 01-JUL-1976 Tested at NEADB
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10. REFERENCES

- A. Daneri, G. Toselli:
  'SHREDI: A Bidimensional Removal-Diffusion Shielding Code.
  Fundamentals and Results'
  N.S.E. (to be published)
NEA-0466/01, included references:
- A. Daneri, G. Toselli:
"SHREDI: A Removal-Diffusion Shielding Code for X-Y
and R-Z Geometries"
RT/FIMA(74)2
-A. Daneri, G. Toselli:
"The Code SHREDI: Input Data for Using The Nuclear
Data Library"
RT/FIMA(76)3
- A.Daneri, L.Martelli, G.Toselli
"SHREDI: A Removal-Diffusion Shielding Code for X-Y
and R-Z Geometries.
(CNEN, Bologna, 11 Oct.1972)
- A.Daneri, G.Toselli:
Letter to Dr. Garcia De Viedma, ISPRA.
(21 May 1976).
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11. MACHINE REQUIREMENTS

Approximately 420 kbytes of core storage.
The logical numbers of the data sets on peripheral units (tapes or discs) are: 2,3,4,8,9,10,11.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0466/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  OS/370 with MVT or MVS.
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  SHREDI is an overlay program.
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15. NAME AND ESTABLISHMENT OF AUTHOR

   A. Daneri and G. Toselli
   Centro di Calcolo
   CNEN
   Via Mazzini, 2
   40138 Bologna
   Italy.
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16. MATERIAL AVAILABLE
NEA-0466/01
File name File description Records
NEA0466_01.001 SOURCE PROGRAM (F4) 7673
NEA0466_01.002 OVERLAY CARDS 40
NEA0466_01.003 DD CARDS FOR THE EXECUTION 16
NEA0466_01.004 SAMPLE PROBLEM INPUT DATA 936
NEA0466_01.005 SAMPLE PROBLEM PRINTED OUTPUT 16281
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: finite difference method, neutron diffusion equation, neutron flux, r-z, removal-diffusion, shielding, two-dimensional, x-y.