Computer Programs

NEA-0363 ANISN-FONTENAY.

NEA-0363 ANISN-FONTENAY.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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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. Rules for end-users 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.