1. NAME AND TITLE
SAND II: Neutron Flux Spectra Determination by Multiple Foil Activation - Iterative
Method. We recommend PSR-345/SNL-SAND-II.
AUXILIARY ROUTINES
CSTAPE: Generates Cross-Section Data Library for Calculation of Foil Activities.
SLACTS: Generates Spectral and Activities Data for SLTAPE.
SLTAPE: Generates Reference Spectrum Data Library.
SAND II: Neutron Flux Spectra Determination.
DIF: Set of Function Routines.
An early version (1968) of SAND was received through the services of the General Electric
Company, TEMPO, Data Center, Santa Barbara, California, and Computer Sciences, Richland
Washington. Many revisions have been made as the result of user feedback and interaction with
the American Society for Testing and Materials (ASTM) Standards Committee E10. Nuclear
Technology and Applications and Subcommittee E10.05 Nuclear Radiation Metrology. The SAND
II code package is included in the ASTM Proposed Standard Recommended Practices for the
Application of Neutron Spectrum Adjusted Methods in Reactor Surveillance. The PC version
which was packaged in September 1993 is a conversion of the C00112/I3675/00 release last
updated in August 1977.
2. CONTRIBUTORS
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.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; CDC 6600/7600 C00112/C7600/00 and IBM 360/75/91 C00112/I3675/00 FORTRAN 77; IBM PC C00112/IBMPC/01.
4. NATURE OF PROBLEM SOLVED
Neutron energy spectra are determined by an analysis of experimental activation detector data.
5. 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.
A reaction cross-section library is provided with the code.
6. RESTRICTIONS OR LIMITATIONS
None noted.
7. TYPICAL RUNNING TIME
Estimated running time of sample problem: 23 minutes on the IBM 360/75;
PC times on Northgate M86/66: CSTAPE = 16.0 sec.
SLACTS2 = 6.5 sec.
SLACTS3 = 7.0 sec.
SLACTS4 = 26.0 sec.
SLTAPE = 1.5 sec.
SANDII = 75.0 sec. (allowing time to view graphs)
8. COMPUTER HARDWARE REQUIREMENTS
The code is operable on IBM 360/75/91, CDC 6600/7600, and 80386/80486 PCs with a
coprocessor.
9. COMPUTER SOFTWARE REQUIREMENTS
Standard FORTRAN IV compilers may be used. The Lahey F77L3/EM32 Fortran compiler
version 5.01 was used to create the executables included in the package.
10. REFERENCES
F. B. K. Kam, "Notes to User's" (January 1969).
B. Cross, SAND II/CSTAPE (Memo) (June 1975).
W. N. McElroy, S. Berg, T. Crockett, 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 II) and Associated Codes," AFWL-TR-67-41 (September 1967).
W. N. McElroy and 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. Simons 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. CONTENTS OF CODE PACKAGE
Included are the referenced documents and one (1.2MB) DOS diskette which contains the
source codes, data libraries, and input for a sample problem, and an output listing from running the
problem for each of the packaged codes and each hardware version. The PC version includes the
executables.
12. DATE OF ABSTRACT
May 1969; updated July 1981, September 1991, September 1993, January 1994.
KEYWORDS: ACTIVATION DETECTOR; UNFOLDING; NEUTRON; MICROCOMPUTER