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NEA-0363 ANISN-FONTENAY.

ANISN-FONTENAY, 1-D Planar, Spherical, Cylindrical Neutron Transport and Gamma Transport with Deep Penetration

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1. NAME OR DESIGNATION OF PROGRAM:  ANISN-FONTENAY.
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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
ANISN-FONTENAY NEA-0363/01 Tested 01-APR-1973

Machines used:

Package ID Orig. computer Test computer
NEA-0363/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The ANISN system treats neutron and gamma transport in one-dimensional plane, spherical and cylinder geometry. The multigroup cross sections prepared by the programs LIANE and SUPERTOG are processed by the program RETTOG, which produces a binary library with Legendre expansions. The binary library can be updated and edited with the program LGR/B. The photon multigroup cross sections are created with the program GAMLEG/A. If  the bulk of the data is too large, the program TAPEMA produces a special group-by-group library. The volume sources are calculated from a reduced set of input data and punched in a format suitable for input to ANISN, using the program PRESOU. The program ANISN calculates fluxes by groups, space intervals, angle and any number of reaction rates. The energy and space dependent fluxes are stored  on tape and can be reprocessed, edited and plotted with the program  ANISEX, which also permits to calculate supplementary reaction rates. The program ANISN can condense cross sections into a reduced  number of groups. The ANISN system is used as a reference system for the evaluation of approximation methods (space-diffusion or point- kernel) or forthe preparation of multigroup libraries for 2- dimensional transport codes (DOT). In particular it is used for shielding problems with high attenuation in water reactors and fast  reactors.
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4. METHOD OF SOLUTION

Method of discrete ordinates. The program has been designed to treat deep penetration with detailed calculation of spectrum as function of angle. Tests for pointwise convergence have also been introduced.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The complexity of the problem is limited by the storage size.
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6. TYPICAL RUNNING TIME:  0.5 to 15 minutes.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

Multigroup neutron cross section calculation with SUPERTOG from ENDF/B or with LIANE from LINDA.
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9. STATUS
Package ID Status date Status
NEA-0363/01 01-APR-1973 Tested at NEADB
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10. REFERENCES

- R. Douglas O'Dell and Raymond E. Alcouffe:
Transport Calculations for Nuclear Analyses: Theory and Guidelines    for Effective Use of Transport Codes
  LA-10983-MS and UC-32 (September 1987).
NEA-0363/01, included references:
- Ch. Devillers:
  Systeme ANISN - Description et mode d'utilisation du programme aux
  ordonnees discretes ANISN et des programmes auxiliaires
  NEA-N-1358 (Octobre 1970).
- G. Brandicourt et J. de Scheemaecker:
  Systeme ANISN - Programme LGR/B pour la maintenance des bandes
  bibliotheques ANISN avec tracage de courbes de sections efficaces
  CEA-N-1335, rapport No.2 (Novembre 1970).
- C. Dupont:
  Systeme ANISN - Programme ANISEX, exploitation des resultats du
  code ANISN sortis sur bande
  CEA-N-1503, rapport No.3 (Decembre 1971).
- Enrico Sartori:
  Lecture Notes on the Discrete Ordinates Transport Codes ANISN &
  DOT
  Course on Radiation Shielding Methods, Ispra (November 20-24,
  1978)
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0363/01 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: C.Devillers
SERMA/CEN.
Fontenay-Aux-Roses
France.
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16. MATERIAL AVAILABLE
NEA-0363/01
File name File description Records
NEA0363_01.001 INFORMATION 2
NEA0363_01.002 RETTOG SOURCE PROGRAMME 170
NEA0363_01.003 RETTOG JCL+INPUT DATA 15
NEA0363_01.004 TAPEMA SOURCE PROGRAMME 430
NEA0363_01.005 TAPEMA JCL+INPUT DATA 112
NEA0363_01.006 TAPEMA PRINTED OUTPUT 6808
NEA0363_01.007 PRESOU SOURCE PROGRAMME 1324
NEA0363_01.008 PRESOU INPUT DATA 12
NEA0363_01.009 PRESOU PUNCHED OUTPUT 284
NEA0363_01.010 PRESOU PRINTED OUTPUT 140
NEA0363_01.011 ANISN SOURCE PROGRAMME 3360
NEA0363_01.012 ANISN OVERLAY CARDS+JCL+INPUT DATA 334
NEA0363_01.013 ANISN PRINTED OUTPUT 10056
NEA0363_01.014 LGRB SOURCE PROGRAMME 704
NEA0363_01.015 GAMLEG SOURCE PROGRAMME 517
NEA0363_01.016 ANISEX SOURCE PROGRAMME 284
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: cross sections, discrete ordinate method, flux distribution, multigroup, neutrons, one-dimensional, photons, reaction kinetics, shielding, transport theory.