CCC-0255: ANISN-W, 1-D Transport Calculation for Deep Penetration Problems

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

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CCC-0255 ANISN-W. (Abstract last modified 05-DEC-2001)

ANISN-W, 1-D Transport Calculation for Deep Penetration Problems

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

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

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-W CCC-0255/01 Tested ANISN-ASEA CCC-0255/02 Obsolete

Machines used: Package-ID Orig.Computer Test Computer CCC-0255/01 CDC CYBER 172 CDC CYBER 172

3. DESCRIPTION OF PROBLEM OR FUNCTION - ANISN-W solves the one- dimensional Boltzmann transport equation for neutrons or gamma rays in slab, sphere or cylinder geometry. The source may be fixed, fission, or a subcritical combination of the two. Criticality search may be performed on any one of several parameters. Cross sections may be weighted using the space and energy dependent flux generated in solving the transport equation.

4. METHOD OF SOLUTION - The solution technique is an advanced discrete ordinates method which represents a generalization of the method originated by G.C. Wick and greatly developed to curvilinear geometry by B.G. Carlson at Los Alamos Scientific Laboratory. ANISN-W was designed to solve deep-penetration problems in which angle-dependent spectra are calculated in detail. The principal feature that makes it suitable for such problems is the use of a programming technique with optional data-storage configurations which allows execution of small, intermediate and extremely large problems. ANISN-W also includes a technique for handling general anisotropic scattering, point-wise convergence criteria, and alternate step function difference equations that effectively remove the oscillating flux distributions sometimes found in discrete ordinates solutions.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -
Problem size is limited only by machine size.

6. TYPICAL RUNNING TIME - Depending on problem size, type, and convergence, running time has varied from less than one minute to several hours.

7. UNUSUAL FEATURES OF THE PROGRAM -

8. RELATED AND AUXILIARY PROGRAMS -
DOQ: Discrete Ordinates Quadrature Coefficients Data Generator
ADOQ: Asymmetric Discrete Ordinates Quadrature Coefficients Data Generator
GAMLEG-W: Multigroup Photon Transport Cross Section Data Generator
PERT-1D: Linear First Order Perturbation Equation Solver - Using the ANISN-W Forward and Adjoint Angular Fluxes.

9. STATUS
CCC-0255/01: 01-JAN-1978 Tested at NEADB
CCC-0255/02: 05-DEC-2001 Obsolete

10. REFERENCES  -
-   R.G. Soltesz and R.K. Disney :
    Nuclear Rocket Shielding Methods, Modification, Updating, and
    Input Data Preparation
    WANL-PR-(LL)-034 (August 1970):
    Volume 2, Section 2 "GAMLEG-W"
    Volume 4, "One-Dimensional Discrete Ordinates Transport
               Technique"
    Volume 5, "Descriptions of DOQ and ADOQ"
-   WANL-PR-(LL)-040 (December 1971), Workshop Notes.
-   R.K. Disney et al. :
    ANISN-W
    WANL-TME-2778 (February 1971)
-   R.G. Soltesz :
    Revised WANL ANISN Program User's Manual
    WANL-TMI-1967, Supplement 1969
-   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)
CCC-0255/01:
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)

11. MACHINE REQUIREMENTS -
CDC 6600: ANISN-W uses one tape unit excluding standard I-O.
It is channel dependent. It uses a punch and a printer.

12. PROGRAMMING LANGUAGE(S) USED -
CCC-0255/01: FORTRAN-IV

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -
A FORTRAN IV compiler is required and overlay is used. Punched card output optional, controlled by input.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
Contributed by : Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.

16. MATERIAL AVAILABLE -
CCC-0255/01:
CCC0255_01.001    SOURCE PROGRAM F4-BCD                            4110 records
CCC0255_01.002    SAMPLE PROBLEM DATA                               793 records
CCC0255_01.003    SAMPLE PROBLEM PUNCHED OUTPUT                      36 records
CCC0255_01.004    SAMPLE PROBLEM PRINTED OUTPUT                    4303 records
CCC0255_01.005    FIDO SOURCE FOR ANISN-W F4-BCD                    230 records
CCC0255_01.006    ADJOINT WEIGHTING ROUTINE F4-BCD                  690 records
CCC0255_01.007    ADOQ SOURCE F4-BCD                                182 records
CCC0255_01.008    ADOQ INPUT DATA                                   425 records
CCC0255_01.009    ADOQ PUNCHED OUTPUT                               886 records
CCC0255_01.010    DOQ SOURCE F4-BCD                                 636 records
CCC0255_01.011    DOQ INPUT DATA                                     24 records
CCC0255_01.012    DOQ PUNCHED OUTPUT                                241 records
CCC0255_01.013    FFREAD SOURCE F4-BCD                              119 records
CCC0255_01.014    FFPUN + FLTFX SOURCE F4-BCD                       148 records
CCC0255_01.015    PERT1D SOURCE F4-BCD                              988 records
CCC0255_01.016    GAMLEG-W SOURCE F4-BCD                            617 records
CCC0255_01.017    GAMLEG LIBRARY BCD                                950 records

17. CATEGORIES  -

- C.  Static Design Studies
- J.  Gamma Heating and Shield Design

Keywords: ABSORPTION, ANISOTROPIC SCATTERING, BUCKLING, CROSS SECTIONS, CYLINDERS, DISCRETE ORDINATE METHOD, FISSION, GAMMA RADIATION, NEUTRON TRANSPORT THEORY, ONE-DIMENSIONAL, SHIELDING, SLABS, SPHERES, TRANSPORT THEORY

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