CCC-0254: ANISN, 1-D Neutron Transport and Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering

Machines used: Package-ID Orig.Computer Test Computer CCC-0254/03 IBM 360 series IBM 360 series CCC-0254/05 UNIVAC 1110 UNIVAC 1110 CCC-0254/07 DEC VAX series MICROVAX CCC-0254/08 CRAY X-MP CRAY Y-MP CCC-0254/10 RISC 6000 RISC 6000 CCC-0254/11 PC-80386 PC-80486

3. DESCRIPTION OF PROBLEM OR FUNCTION - ANISN 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 and extended to curvi- linear geometry by B.G. Carlson at Los Alamos Scientific Laboratory. ANISN was designed to solve deep-penetration problems in which angle-dependent spectra are calculated in detail. The principal feature that makes ANISN 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 also includes a technique for handling general ani- sotropic scattering, pointwise convergence criteria, and alternate step function difference equations that effectively remove the oscillating flux distributions sometimes found in discrete ordinates solutions. Improvements are made for the Cray and IBM RISC versions. They include the addition of 3 arrays; 29$ (regions by interval) 59$ (unit # for input and output), and 60$ (Kword of storage).

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. On the IBM 3033 the adjoint air neutron sample problem required about 45 seconds. The other ten sample cases ran in about 30 seconds. On the Cray XMP-14, the adjoint problem ran in .2 minute. The 10 sample problems took .11 minute. On a Northgate 486/66 most sample problems ran in 5 seconds or less. The RISC 6000 took approximately 5 seconds to run the 10 sample problems.

CCC-0254/05:

NEA-DB executed all test cases on UNIVAC 1110 in 8 CPU minutes.

CCC-0254/07:

NEA-DB executed the test cases included in this package on a MicroVAX computer. Execution times required were:
3 minutes 14 seconds for test case 1; 4 minutes 37 seconds for test case 2.

CCC-0254/08:

NEA-DB compiled this version of the code on a Cray YMP-EL computer and executed the test cases. The following CPU times were required for the test cases: adjoint air neutron case: 35 secs; the other 10 test cases: 27 secs.

7. UNUSUAL FEATURES OF THE PROGRAM -

9. STATUS
CCC-0254/01: 14-OCT-1982 Obsolete
CCC-0254/02: 24-OCT-1995 Obsolete
CCC-0254/03: 01-JUL-1979 Tested at NEADB
CCC-0254/05: 07-OCT-1982 Tested at NEADB
CCC-0254/06: 25-MAY-2001 Obsolete
CCC-0254/07: 16-JUN-1988 Tested at NEADB
CCC-0254/08: 22-MAR-1993 Tested at NEADB
CCC-0254/09: 24-OCT-1995 Obsolete
CCC-0254/10: 27-DEC-1995 Tested at NEADB
CCC-0254/11: 03-JUL-1995 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).
- M.G. Nurdin:
  Ameliorations apportees a l'utilisation des codes de transport
  ANISN, DOT et MORSE
  Note Technique No. 245 (EXPER), 40083/CAD/NUC5 (18 January 1990)
- F. Wasastjerna:
  Implementation of ANISN on the HP/UNIX System
  VTT Technical Report RFD-19/92 (August 1992)
CCC-0254/03:
- W.W. Engle Jr.:
  A Users Manual for ANISN, A One Dimensional Discrete Ordinates
  Transport Code with Anisotropic Scattering
  K-1693  (Updated June 1973)
- W.A. Rhoades:
  The ACL1 Program for Cross Section Library Management
  ORNL-TM-4015  (December 1972)
- Comparison of Iteration Techniques
  Reprint from "Transactions of American Nuclear Society",
  Vol. 2, No. 1, (June 1968)
- R.W. Roussin:
  Group Averaging of Cross Sections with ANISN
  (March 1971)
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross Section Data to a
  Smaller Number of Groups
  ORNL-TM-3049  (May 1969)
- W.W. Engle, M.A. Boling and B.W. Closton:
  DTF-II, A One Dimensional Multigroup Neutron Transport Program
  NAA-SR-10951  (March 1966)
- Sumer Sahin:
  AWNL: A Computer Program to Calculate the Adjoint Weighted
  Neutron Lifetime
  (January 1979)
- Details of Corrections Made to ANISN
  RSIC Newsletter No. 210  (June 1982)
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
CCC-0254/05:
- "Le Code ANISN - Version ARMEMENT"
  Internal Note
- G. Nurdin:
  Utilisation du Code ANISN en Geometrie Plane pour un Rayonnement
  Monodirectionel: Cas des Neutrons, des Gammas et des X
  Note Technique n. 39  (Juillet 1984)
- G. Nurdin:
  Le Code de Transport ANISN: Remarques Pratiques sur son
  Utilisation pour des Problemes de Protection et Examples
  d' Application.
  Note Technique n. 65  (Juin 1986)
- W.W. Engle Jr.:
  A Users Manual for ANISN, A One Dimensional Discrete Ordinates
  Transport Code with Anisotropic Scattering
  K-1693  (Updated June 1973)
- W.A. Rhoades:
  The ACL1 Program for Cross Section Library Management
  ORNL-TM-4015  (December 1972)
- Comparison of Iteration Techniques
  Reprint from "Transactions of American Nuclear Society",
  Vol. 2, No. 1, (June 1968)
- R.W. Roussin:
  Group Averaging of Cross Sections with ANISN
  (March 1971)
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross Section Data to a
  Smaller Number of Groups
  ORNL-TM-3049  (May 1969)
- W.W. Engle, M.A. Boling and B.W. Closton:
  DTF-II, A One Dimensional Multigroup Neutron Transport Program
  NAA-SR-10951  (March 1966)
- Sumer Sahin:
  AWNL: A Computer Program to Calculate the Adjoint Weighted
  Neutron Lifetime
  (January 1979)
- Details of Corrections Made to ANISN
  RSIC Newsletter No. 210  (June 1982)
- E. Sartori:
  Lecture Notes on the Discrete Ordinates Transport
  Codes ANISN & DOT.
  "Course on Radiation Shielding Methods", Ispra (Nov.20-24, 1978)
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
CCC-0254/07:
- W.W. Engle Jr.:
  A Users Manual for ANISN, A One Dimensional Discrete Ordinates
  Transport Code with Anisotropic Scattering
  K-1693  (Updated June 1973)
- W.A. Rhoades:
  The ACL1 Program for Cross Section Library Management
  ORNL-TM-4015  (December 1972)
- Comparison of Iteration Techniques
  Reprint from "Transactions of American Nuclear Society",
  Vol. 2, No. 1, (June 1968)
- R.W. Roussin:
  Group Averaging of Cross Sections with ANISN
  (March 1971)
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross Section Data to a
  Smaller Number of Groups
  ORNL-TM-3049  (May 1969)
- W.W. Engle, M.A. Boling and B.W. Closton:
  DTF-II, A One Dimensional Multigroup Neutron Transport Program
  NAA-SR-10951  (March 1966)
- Sumer Sahin:
  AWNL: A Computer Program to Calculate the Adjoint Weighted
  Neutron Lifetime
  (January 1979)
- Details of Corrections Made to ANISN
  RSIC Newsletter No. 210  (June 1982)
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
CCC-0254/08:
- Rob Tayloe:
  "READ.ME"
  Informal Notes (1991).
- Modifications Included in the July 1988 ANISN Updates
  ORNL Informatal Notes (July 1988).
- ANISN Updates and Additional Information
  (1971-1977).
- W.W. Engle Jr.:
  A Users Manual for ANISN, A One Dimensional Discrete Ordinates
  Transport Code with Anisotropic Scattering
  K-1693 (Updated June 1973).
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross Section Data to a
  Smaller Number of Groups
  ORNL-TM-3049 (May 1969).
- W.W. Engle, M.A. Boling and B.W. Closton:
  DTF-II, A One Dimensional Multigroup Neutron Transport Program
  NAA-SR-10951 (March 1966).
- W.W. Engle Jr., and F.R. Mynatt:
  A Comparison at Two Methods of Inner Iteration Convergence
  Acceleration in Discrete Ordinates Codes
  Reprint from "Transactions of American Nuclear Society",
  Vol. 2, No. 1, (June 1968).
- L.M. Petrie:
  Informal Notes on Use of ITIME Assembler Routine in IBM Version
  ORNL (May 1973).
- Enrico Sartori:
  Note to all recipients of various versions of ANISN
  NDB/93/0931 (27 August, 1993)
CCC-0254/10:
- W.W. Engle et al.:
  A Comparison at Two Methods of Inner Iteration Convergence
  Acceleration in Discrete Ordinates Codes,
  Transactions of ANS, Vol.II, No.1 (June 1968)
- ANISN Updates and Additional Information (1971-1977)
- L.M. Petrie:
  Informal Notes on Use of ITIME Assembler Routine in IBM Version,
  ORNL (May 1973)
- Modifications Included in the July 1988 ANISN Updates
  ORNL Informal Notes (July 1988)
- "README.1ST", IBM RISC Implementation Notes (4/94)
- W.W. Engle et al.:
  ANISN, A One-Dimensional Discrete Ordinates Transport Code with
  Anisotropic Scattering,
  K-1693 (March 1967)
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross-Section Data to
  a Smaller Number of Groups,
  ORNL-TM-3049 (May 1969)
- W.W. Engle et al.:
  DTF-II, A One-Dimensional Multigroup Neutron Transport Program,
  NAA-SR-10951 (March 1966)
CCC-0254/11:
- W.W. Engle et al.:
  A Comparison at Two Methods of Inner Iteration Convergence
  Acceleration in Discrete Ordinates Codes,
  Transactions of ANS, Vol.II, No.1 (June 1968)
- ANISN Updates and Additional Information (1971-1977)
- L.M. Petrie:
  Informal Notes on Use of ITIME Assembler Routine in IBM Version,
  ORNL (May 1973)
- Modifications Included in the July 1988 ANISN Updates
  ORNL Informal Notes (July 1988)
- "README.1ST", IBM RISC Implementation Notes (4/94)
- W.W. Engle et al.:
  ANISN, A One-Dimensional Discrete Ordinates Transport Code with
  Anisotropic Scattering,
  K-1693 (March 1967)
- R.W. Roussin:
  Using ANISN to Reduce the DLC-2/100-Group Cross-Section Data to
  a Smaller Number of Groups,
  ORNL-TM-3049 (May 1969)
- W.W. Engle et al.:
  DTF-II, A One-Dimensional Multigroup Neutron Transport Program,
  NAA-SR-10951 (March 1966)

11. MACHINE REQUIREMENTS - ANISN-ORNL is operable on the IBM 3033 (A), CRAY XMP-2 (B), VAX family (c) or DEC-10, DEC-20 (G) computers. The PC version runs on 386 (with 387 co-processor) or 486 personal computers. It requires 4 megabytes of memory and a 20 megabyte hard disk and a math co-processor. Faster run time is achieved with 5 or more MB of memory.

CCC-0254/11:

The NEA Data Bank installed the program on a DELL 466/L PC/80486 with 67 MHz and 17 MBytes of RAM.

12. PROGRAMMING LANGUAGE(S) USED -
CCC-0254/03: FORTRAN-IV
CCC-0254/05: FORTRAN-IV
CCC-0254/07: FORTRAN-77
CCC-0254/08: FORTRAN-77
CCC-0254/10: FORTRAN
CCC-0254/11: FORTRAN

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - The IBM version runs under OS/VS2(MVS) using the VS FORTRAN compiler with the 'LANGLVL(66)' option or a FORTRAN H compiler. The CRAY version uses the CFT compiler with FORTLIB under CTSS; under UNICOS, the CFT77 compiler is used. The VAX version runs under VMS 4.6 using the VMS FORTRAN (version 4.7) compiler with the /NOOPTIMIZE and /NOF77 switches. The DEC-10 version requires a FORTRAN 77 compiler. The Lahey FORTRAN F77-EM/32 version 4.00 compiler was used with the virtual memory linker under the Lahey/ERGO OS/386 2.1.05 operating system to create the executable. The program will run under DOS 3.3 or higher.

CCC-0254/07:

VAX/VMS V4.4.

CCC-0254/08:

The program was run under UNICOS rel.6.1.6 using the CFT77 compiler.

CCC-0254/11:

The program was installed under MS-DOS 6.2. The source files were compiled using the Lahey F77L-EM/32 Fortran-77 compiler Version 5.20.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -
ANISN-ARMEMENT (CCC-0254/05): This UNIVAC version of the ANISN code is based on the IBM version of ANISN-ORNL (CCC-0254/03). Subroutine CORESZ dynamically adjusts the size of COMMON/BULKBU/ to the problem size.

15. NAME AND ESTABLISHMENT OF AUTHOR -
  ORNL, Oak Ridge, Tennessee, U.S.A (A and B)
  Infintum Sciences Limited, Ottawa, Ontario, Canada (C)
  Goodyear Atomic Corp., Piketon, Ohio, U.S.A. (G)
  Battelle, Columbus, Ohio, U.S.A (H)

17. CATEGORIES  -

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

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