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CCC-0255 ANISN-W.

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

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1. NAME OR DESIGNATION OF PROGRAM:  ANISN-W.
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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-W CCC-0255/01 Tested 01-JAN-1978

Machines used:

Package ID Orig. computer Test computer
CCC-0255/01 CDC CYBER 172 CDC CYBER 172
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
Problem size is limited only by machine size.
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6. TYPICAL RUNNING TIME

Depending on problem size, type, and convergence, running time has varied from less than one minute to several hours.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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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.
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9. STATUS
Package ID Status date Status
CCC-0255/01 01-JAN-1978 Tested at NEADB
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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, included references:
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
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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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0255/01 FORTRAN-IV
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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.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

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