NEA-0363: ANISN-FONTENAY, 1-D Planar, Spherical, Cylindrical Neutron Transport and Gamma Transport with Deep Penetration

OECD Nuclear Energy Agency / L'Agence pour l'énergie nucléaire

OECD-OCDE

[Program Service | Recent programs]

NEA-0363 ANISN-FONTENAY. (Abstract last modified 01-APR-1973)

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

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION OF PROGRAM - ANISN-FONTENAY.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status ANISN-FONTENAY NEA-0363/01 Tested

Machines used: Package-ID Orig.Computer Test Computer NEA-0363/01 IBM 370 series IBM 370 series

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.

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - The complexity of the problem is limited by the storage size.

6. TYPICAL RUNNING TIME - 0.5 to 15 minutes.

7. UNUSUAL FEATURES OF THE PROGRAM -

8. RELATED AND AUXILIARY PROGRAMS - Multigroup neutron cross section calculation with SUPERTOG from ENDF/B or with LIANE from LINDA.

9. STATUS
NEA-0363/01: 01-APR-1973 Tested at NEADB

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:
- 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)

11. MACHINE REQUIREMENTS -

12. PROGRAMMING LANGUAGE(S) USED -
NEA-0363/01: FORTRAN-IV

13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED -

14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
C.Devillers
SERMA/CEN.
Fontenay-Aux-Roses
France.

16. MATERIAL AVAILABLE -
NEA-0363/01:
NEA0363_01.001    INFORMATION                                         2 records
NEA0363_01.002    RETTOG   SOURCE PROGRAMME                         170 records
NEA0363_01.003    RETTOG   JCL+INPUT DATA                            15 records
NEA0363_01.004    TAPEMA   SOURCE PROGRAMME                         430 records
NEA0363_01.005    TAPEMA   JCL+INPUT DATA                           112 records
NEA0363_01.006    TAPEMA   PRINTED OUTPUT                          6808 records
NEA0363_01.007    PRESOU   SOURCE PROGRAMME                        1324 records
NEA0363_01.008    PRESOU   INPUT DATA                                12 records
NEA0363_01.009    PRESOU   PUNCHED OUTPUT                           284 records
NEA0363_01.010    PRESOU   PRINTED OUTPUT                           140 records
NEA0363_01.011    ANISN    SOURCE PROGRAMME                        3360 records
NEA0363_01.012    ANISN    OVERLAY CARDS+JCL+INPUT DATA             334 records
NEA0363_01.013    ANISN    PRINTED OUTPUT                         10056 records
NEA0363_01.014    LGRB     SOURCE PROGRAMME                         704 records
NEA0363_01.015    GAMLEG   SOURCE PROGRAMME                         517 records
NEA0363_01.016    ANISEX   SOURCE PROGRAMME                         284 records

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

Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search