CCC-0657: BETA-S, Multi-Group Beta-Ray Spectra

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CCC-0657 BETA-S 3.1. (Abstract last modified 21-AUG-2001)

BETA-S, Multi-Group Beta-Ray Spectra

Abstract Table of Contents:

1. NAME OR DESIGNATION OF PROGRAM - BETA-S 3.1.

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 BETA-S 3.1 CCC-0657/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CCC-0657/01 Many Computers

3. DESCRIPTION OF PROGRAM OR FUNCTION - BETA-S calculates beta-decay source terms and energy spectra in multigroup format for time-dependent radionuclide inventories of actinides, fission products, and activation products. Multigroup spectra may be calculated in any arbitrary energy-group structure. The code also calculates the total beta energy release rate from the sum of the average beta-ray energies as determined from the spectral distributions. BETA-S also provides users with an option to determine principal beta-decaying radionuclides contributing to each energy group. The CCC-545/SCALE 4.3 (or SCALE4.2) code system must be installed on the computer before installing BETA-S, which requires the SCALE subroutine library and nuclide-inventory generation from the ORIGEN-S code.

4. METHODS - Well-established models for beta-energy distributions are used to explicitly represent allowed, and 1st-, 2nd - and 3rd -forbidden transition types. Forbidden non-unique transitions are assumed to have a spectral shape of allowed transitions. The multigroup energy spectra are calculated by numerically integrating the energy distribution functions using an adaptive Simpson's Rule algorithm. Nuclide inventories are obtained from a binary interface produced by the ORIGEN-S code. BETA-S calculates the spectra for all isotopes on the binary interface that have associated beta-decay transition data in the ENSDF-95 library, developed for the BETA-S code. This library was generated from ENSDF data and contains 715 materials, representing approximately 8500 individual beta transition branches.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - The algorithms do not treat positron decay transitions or internal conversion electrons. The neglect of positron transitions in inconsequential for most applications involving aggregate fission products, since most of the decay modes are via electrons. The neglect of internal conversion electrons may impact on the accuracy of the spectrum in the low-energy region (less than 1MeV). Approximations in the representation of the spectral shape factors for the forbidden transitions may lead to poor spectral representation for some nuclides.

6. TYPICAL RUNNING TIME - Typical problems require about 20 seconds to complete on an IBM RS/6000-25T.

7. UNUSUAL FEATURES -

8. RELATED OR AUXILIARY PROGRAMS - ENSDF-95: Beta-decay transition data based on the Evaluated Nuclear Structure Data Files maintained by NNDC at Brookhaven National Library.

9. STATUS
CCC-0657/01: 21-AUG-2001 Masterfiled Arrived

10. REFERENCES  -
CCC-0657/01:
- I.C. Gauld and S.G. King:
  BETA-S: A Code to Calculate Multigroup Beta Spectra.
  RC-1564 (COG-96-33-I) (April 1996)

11. HARDWARE REQUIREMENTS - BETA-S has been installed and verified on IBM RS/6000 and HP-750 workstations. Porting to any platform for which the SCALE system is available should require minimal effort.

12. PROGRAMMING LANGUAGE -CCC-0657/01: FORTRAN-77

13. SOFTWARE REQUIREMENTS - BETA-S has been installed on Unix and DOS operating systems. A Fortran 77 compiler is required. No executables are included in this distribution. Several C language utility routines, primarily for system quality assurance functions, are obtained from the SCALE subroutine library for the Unix version.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHORS -
Contributed by:
                    Radiation Safety Information Computational Center
                    Oak Ridge National Laboratory
                    Oak Ridge, Tennessee, U. S. A.
Developed by:
                    Atomic Energy of Canada Limited
                    Whiteshell Laboratories
                    Manitoba, CANADA

16. MATERIAL AVAILABLE -CCC-0657/01:
Readme. rsi Information file
README.PC Information file
README.TXT Information file
ENSDF-95.1 Data library
OUT1 Output file
OUT2 Output file
DATIM.PC PC file
F77L3.FIG PC file
FHLPR.PC PC file
FILNAM.FOR PC file
FINDQA.PC PC file
FULNAM.PC PC file
GETFILE.PC PC file
JOBNUM.PC PC file
LISTQA.PC PC file
LTTR.PC PC file
MAK_BETA.BAT PC file
MAK_BETA.CMP PC file
MAK_BETA.DAT PC file
MAK_BETA.LNK PC file
MESAGE.FOR PC file
OPNFIL.PC PC file
VERGET.PC PC file
IN1 Sample problems
IN2 Sample problems
BETAS.F Main program routine in BETA-S
BLKDTA00.F Assigns coefficients of the second-order polynomial
CKCHAR.F Determines if CHAR is a letter between A and Z
COSIMP.F Evaluates definitive integrals using Sonmpson's Rule algorithm
DIST1F Beta-energy distribution function for 1st forbidden unique transition types
DIST2F Beta-energy distribution function for 2nd forbidden unique transition types
DIST3F Beta-energy distribution function for 3rd forbidden unique transition types
DISTA.F Beta-energy distribution function for the allowed transitions
DISTE1F.F Energy-weighted distrib.function for 1st forbidden unique transitions
DISTE2F.F Energy-weighted distrib.function for 2nd forbidden unique transitions
DISTE3F.F Energy-weighted distrib.function for 3rd forbidden unique transitions
DISTEA.F Energy-weighted distribution function for allowed transitions
ERROR.F Print error message C and terminate program using STOP 777
FINDF.F Reads nuclear decay data from data library for nuclide NUCLI
FREE.F Performs free-form card input
GETSIZ.F Reads 1st record of binary nuclide composition interface
HALF.F Converts nuclide half-life to decay constant having s-1 units
LIMITS.F Returns array index limits for nuclide groups
LOADI.F Loads isotopic inventories from binary nuclide inventory interface
NORMALIZ.F Returns integral of energy distribution function over their energy range
PACKC.F Inserts character C into the Kth character position of array Z
RUIN.F Reads input file for BETA-S
SPECTRA.F Calculates beta-energy spectrum for a single transition
TIMES.F Return character headings for each time step
XBETA.F Calculates & prints gross beta activity if requested
XSPEC.F Calculates & prints multi-group energy spectra for specified time steps
XTRANS.F Reads beta-decay transition library data into memory

17. CATEGORIES -

- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: ACTINIDES, ACTIVATION ANALYSIS, BETA SPECTRA, FISSION PRODUCTS, MULTIGROUP