CCC-0112: SAND-2, Neutron Flux Spectra from Multiple Foil Activation Experiment

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CCC-0112 SAND-2. (Abstract last modified 19-APR-1994)

SAND-2, Neutron Flux Spectra from Multiple Foil Activation Experiment

Abstract Table of Contents:

1. NAME OR DESIGNATION OF PROGRAM. SAND-2. Neutron flux spectra determination by multiple foil activation - iterative method.

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 SAND-2 CCC-0112/01 Obsolete SAND-2 CCC-0112/02 Obsolete SAND-2 CCC-0112/03 Obsolete SAND-II CCC-0112/04 Tested

Machines used: Package-ID Orig.Computer Test Computer CCC-0112/04 PC-80486 PC-80486

3. NATURE OF PHYSICAL PROBLEM SOLVED.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
  FORMAT: SAND-II
  NUMBER OF GROUPS: --
  NUCLIDES:
3 COVERS
Cd, B, Au
40 FOILS
Cu-63(n,a)Co-60M, Ag-109(n,g)Ag-110M, Co-59(n,a)Mn-56,
Fe-58(n,g)Fe-59, Ni-60(n,p)Co-60, Cu-63(n,a)Co-60, Ni-58(n,p)Co-58, FP-Pu-239(n,f), Sc-45(n,g)Sc-46, Na-23(n,g)Na-24, Th-232(n,g)Th-233, U-238(n,g)U-239, Au-197(n,g)Au-198, Co-59(n,g)Co-60,
In-115(n,g)In-116M, Mn-55(n,g)Mn-56, Cu-63(n,g)Cu-64,
FP-Th-232(n,f), Zn-64(n,p)Cu-64, Fe-54(n,p)Mn-54, S-32(n,p)P-32,
Si-28(n,p)Al-28, S-34(n,a)Si-31, Mg-24(n,p)Na-24, Cl-35(n,a)P-32,
Ni-58(n,2n)Ni-57, I-127(n,2n)I-126, Zr-90(n,2n)Zr-89,
Ti-46(n,p)Sc-46, Ti-47(n,p)Sc-47, Ti-48(n,p)Sc-48, Cu-63(n,2n)Cu-62, P-31(n,p)Si-31, Fe-56(n,p)Mn-56, Al-27(n,p)Mg-27, FP-Np-237(n,f),
FP-U-238(n,f), FP-U-235(n,f), Al-27(n,a)Na-24, In-115(n,n)M.
Additional cross sections provided cover the following nuclides:
Li-6, B-10, Na-23, Co-59, Au-197, Tm-232, U-235, U-238, Np-237,
Pu-239, Cu-63.
  ORIGIN: Library distributed with the program.
  WEIGHTING SPECTRUM: --
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
Neutron energy spectra are determined by an analysis of experimental activation detector data.

4. METHOD OF SOLUTION. An iterative perturbation method is used to obtain a 'best fit' neutron flux spectrum for a given input set of infinitely dilute foil activities. The calculational procedure consists of the selection of a known flux spectrum form to serve as the initial approximation to the solution, and subsequent iteration to a form acceptable as an appropriate solution. The solution is specified either as time-integrated flux (fluence) for a pulsed environment or as a flux for a steady-state neutron environment.
The SAND-II Data Library, distributed with the package contains the following:
3 COVERS
Cd, B, Au
40 FOILS
Cu63(n,a)CO60M, Ag109(n,g)Ag110M, Co59(n,a)Mn56, Fe58(n,g)Fe59, Ni60(n,p)Co60, Cu63(n,a)Co60, Ni58(n,p)Co58, Pu239(n,f)Fp, Sc45(n,g)Sc46, Na23(n,g)Na24, Th232(n,g)Th233, U238(n,g)U239, Au197(n,g)Au198, Co59(n,g)CO60, In115(n,g)In116M, Mn55(n,g)Mn56, Cu63(n,g)Cu64, Th232(n,f)Fp, Zn64(n,p)Cu64, Fe54(n,p)Mn54, S32(n,p)P32, Si28(n,p)Al28, S34(n,a)Si31, Mg24(n,p)Na24, Cl35(n,a)P32, Ni58(n,2n)Ni57, I127(n,2n)I126, Zr90(n,2n)Zr89, Ti46(n,p)Sc46, Ti47(n,p)Sc47, Ti48(n,p)Sc48, Cu63(n,2n)Cu62, P31(n,p)Si31, Fe56(n,p)Mn56, Al27(n,p)Mg27, Np237(n,f)Fp, U238(n,f)Fp, U235(n,f)Fp, Al27(n,a)Na24, In115(n,n)M.
Additional cross sections provided cover the following nuclides:
Li6, B10, Na23, Co59, Au197, Tm232, U235, U238, Np237, Pu239, Cu63.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM. None noted.

6. TYPICAL RUNNING TIME. Estimated running time of sample problem - 2 - 3 minutes on the IBM 360/75.

CCC-0112/04:

The sample problem was executed at the NEA-DB on a
66-MHz PC/80486. The CPU times required for the different programs are shown in the following table:
                  ------------------
                   Program  | Time
                    name    | (sec)
                  ------------------
                  CSTAPE*   | 13.4
                  SLACTS2   |  6.0
                  SLACTS3   |  6.0
                  SLACTS4   | 23.5
                  SLTAPE    |  0.8
                  SAND-II** | 73.6
                  ------------------
             *  Cross-section library generation
             ** including plot generation

7. UNUSUAL FEATURES OF THE PROGRAM.

9. STATUS
CCC-0112/01: 15-DEC-1994 Obsolete
CCC-0112/02: 09-OCT-1980 Obsolete
CCC-0112/03: 15-DEC-1994 Obsolete
CCC-0112/04: 19-APR-1994 Tested at NEADB

10. REFERENCES  -
- J.G. Kelly:
  Neutron Spectrum Adjustment with SANDII Using Arbitrary Trial
  Functions
  Reactor Dosimetry: Methods, Applications, and Standardization,
ASTM STP 1001, Harry Farrar IV and E.P. Lippincott, Eds. American Society for Testing & Materials, Philadelphia pp. 460-468 (1989)
- J.G. Kelly and P.J. Griffin:
  Comparison of Measured Silicon Displacement Damage Ratios with
  ASTM E-722 and NJOY Calculated Damage, SAND89-2284C
- J.G. Kelly and P.J. Griffin:
  Use of Silicon Bipolar Transistors as Sensors for Neutron Energy
  Spectra Determination, SAND91-0163A
CCC-0112/04:
- F.B.K. Kam:
  Notes to User's
  (January 1969).
- B. Cross:
  SAND-II/CSTAPE (Blue Sheets)
  Memo (June 1975).
- W.N. McElroy, S. Berg, T. Crockett, and R.G. Hawkins:
  A Computer-Automated Iterative Method for Neutron Flux Spectra
  Determination by Foil Activation - Vol. I: A Study of the
  Iterative Method
  AFWL-TR-67-41 (September 1967).
- S. Berg and W.N. McElroy:
  A Computer-Automated Iterative Method for Neutron Flux Spectra
  Determination by Foil Activation - Vol. II: SAND II (Spectrum
  Analysis by Neutron Detectors) and Associated Codes
  AFWL-TR-67-41, Volume II (September 1967).
- W.N. McElroy, S. Berg:
  A Computer-Automated Iterative Method for Neutron Flux Spectra
  Determination by Foil Activation - Vol. IV: Reference Spectrum
  Library for SAND II
  AFWL-TR-67-41 (September 1967).
- S. Berg:
  Modification of SAND II
  BNWL-855 (August 1968).
- R.L. Simmons, and W.N. McElroy:
  Evaluated Reference Cross Section Library
  BNWL-1312 (May 1970).
- M.L. Eaton, and W.L. Wilcoxson:
  Estimating Strengths of Individual Radioisotopes in a Multiple-
  Isotope Source
  Technical Report R-551.

11. MACHINE REQUIREMENTS.

CCC-0112/04:

The sample problem was run at the NEA-DB on a PC DELL 466/L (processor 80486, 66 MHz) with 16 MB of RAM. A total of 4.5 MB of hard disk space are required to install the whole package.

12. PROGRAMMING LANGUAGE(S) USED -
CCC-0112/04: FORTRAN-77

13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED.
Standard FORTRAN IV compilers may be used.

CCC-0112/04:

The program was tested at NEA-DB under MS-DOS 6.0. The source codes were compiled with the Lahey compiler F77L-EM/32 (Version 5.11) and linked with the linker 386LINK.

14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS.

15. NAME AND ESTABLISHMENT OF AUTHOR.
Contributed by:
    Radiation Shielding Information Center
    Oak Ridge National Laboratory
    OAK RIDGE, Tennessee, U. S. A.
Developed by:
    Air Force Weapons Laboratory (RTD)
    Kirtland Air Force Base, New Mexico
    Battelle Memorial Institute Pacific Northwest Laboratory
    RICHLAND, Washington
    Atomics International
    CANOGA PARK, California
    TRW Systems Group, TRW Inc.
    REDONDO BEACH, California
    Oak Ridge National Laboratory
    OAK RIDGE, Tennessee
    Experimental and Mathematical Physics Consultants
    GAITHERSBURG, Maryland

17. CATEGORIES -

- O. Experimental Data Processing

Keywords: ACTIVATION ANALYSIS, ITERATIVE METHODS, NEUTRON FLUX, NEUTRON SPECTRA, PERTURBATION THEORY