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CCC-0657 BETA-S 6.

BETA-S, Multi-Group Beta-Ray Spectra

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1. NAME OR DESIGNATION OF PROGRAM:  BETA-S 6
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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
BETA-S 6 CCC-0657/02 Arrived 28-APR-2009

Machines used:

Package ID Orig. computer Test computer
CCC-0657/02 Linux-based PC,PC Windows
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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 SCALE 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. This release is compatible with SCALE Versions 5.0, 5.1 and 6.
  
The following enhancements were completed in this version:
- the BETA-S source code was converted to modern Fortran 90 standard
- dynamic memory allocation implemented
- the free-format input reading routines were replaced with reading modules in SCALE 5
- added the capability to obtain beta decay branching data from either a binary or card-image format ORIGEN data library (required for compatibility with ORIGEN-ARP)
- corrected an error associated with spectral calculation in highest energy group
- improved spectrum calculation by normalizing spectral energy to evaluated beta energy
- added capability to generate plot files compatible with PlotOPUS program.
Note that default input values were eliminated in this release, so all input variables are now needed. Some libraries now have different numbers of nuclides which can cause problems. To address this, the code now also works with either the card-image nuclear data library or a binary library (e.g., origen-arp). If the ORIGEN inventory file was generated using a binary library, BETAS should be required to use the same library when doing the spectrum calculation to make sure the library is consistent with the nuclide set.
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4. METHODS

Well-established models for the beta-energy distributions are used to explicitly represent allowed, and 1st -, 2nd - and 3rd -forbidden unique transition types. Forbidden non-unique transitions are assumed to have a spectral shape of allowed transitions. Multigroup energy spectra are calculated by numerically integrating 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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The algorithms do not treat positron (beta+) decay transitions or internal conversion electrons. The neglect of beta+ transitions is inconsequential for most applications involving aggregate fission products, since most of the decay modes are via beta-. The neglect of internal conversion electrons may impact on the accuracy of the spectrum in the low-energy region (<1MeV). Approximations in the representation of the spectral shape factors for the forbidden transitions may lead to poor spectral representation for some nuclides.
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6. TYPICAL RUNNING TIME

Typical problems require a few seconds to complete on a Pentium IV 2.66GHz.
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8. RELATED OR AUXILIARY PROGRAMS

SCALE code system not included.
DATA LIBRARY: ENSDF-95: Beta-decay transition data based on the Evaluated Nuclear Structure Data Files maintained by NNDC at Brookhaven National Laboratory.
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9. STATUS
Package ID Status date Status
CCC-0657/02 28-APR-2009 Masterfiled Arrived
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10. REFERENCES
CCC-0657/02, included references:
- I. C. Gauld:
"Upgrade of the Multigroup Beta Calculation Code BETA-S," ORNL paper (December
2008)
- I. C. Gauld and S. G. King:
"BETA-S: A Code to Calculate Multigroup Beta Spectra," RC-1564 (COG-93-33-I)
(April 1996).
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11. HARDWARE REQUIREMENTS

BETA-S has been installed and verified on Personal Computers running Windows and Linux. Porting to any platform for which the SCALE system is available should require minimal effort. Source code is included and can be recompiled if the distributed executables do not work.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0657/02 FORTRAN-90
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13. SOFTWARE REQUIREMENTS

BETA-S has been installed on Linux and Windows XP and Windows Vista operating systems. The code is written in Fortran 90. Several C language utility routines, primarily for system quality assurance functions, are obtained from the SCALE subroutine library. Included executables are compatible with SCALE Versions 5 and 6. They were created by linking with the SCALE 6 subroutine library on these systems:
- Fedora 8 Linux with the 32-bit Intel Fortran 11.0.069 compiler
- Red Hat Enterprise Linux 4 with the 64-bit Intel 10.1.015 compiler
- Windows XP Service Pack 2 with the Intel Fortran 10.1.021 compiler
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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:   Oak Ridge National Laboratory, Oak Ridge, Tennessee
                CANDU Owner Group, Toronto, Ontario, Canada
                Atomic Energy of Canada Limited, Whiteshell Laboratories,
                Manitoba, Canada
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16. MATERIAL AVAILABLE
CCC-0657/02
source files
ENSDF-95 library
test cases
executables
documentation
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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.