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CCC-0661 SOURCES-4C.

SOURCES-4C, Calculating Alpha, N, Fission, Delayed Neutron Sources and Spectra

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1. NAME OR DESIGNATION OF PROGRAM:  SOURCES-4C.
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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
SOURCES-4C CCC-0661/03 Arrived 09-OCT-2002

Machines used:

Package ID Orig. computer Test computer
CCC-0661/03 PC Windows,Linux-based PC,SUN SPARC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SOURCES4C is a code system that determines neutron production rates and spectra from (alpha,n) reactions, spontaneous fission, and delayed neutron emission due to radionuclide decay. In this release the three-region problem was modified to correct several bugs, and new documentation was added to the package. Details are available in the included LA-UR-02-1617 (2002) report.

The code is capable of calculating (alpha,n) source rates and spectra in four types of problems: homogeneous media (i.e., an intimate mixture of alpha-emitting source material and low-Z target material), two-region interface problems (i.e., a slab of alpha-emitting source material in contact with a slab of low-Z target material), three-region interface problems (i.e., a thin slab of low-Z target material sandwiched between alpha-emitting source material and low-Z target material), and (alpha,n) reactions induced by a monoenergetic beam of alpha-particles incident on a slab of target material.

The process of creating a SOURCES input file (tape1) is streamlined with the Los Alamos SOURCES Tape1 Creator and Library Link (LASTCALL) Version 1. Intended to supplement the SOURCES manual, LASTCALL is a simple graphical user interface designed to minimize common errors made during input. The optional application, LASTCALL, consists of a single dialog window launched from an executable (lastcall.exe) on Windows-based personal computers.
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4. METHODS

Spontaneous fission spectra are calculated with evaluated half-life, spontaneous fission branching, and Watt spectrum parameters for 44 actinides. The (alpha,n) spectra are calculated using an assumed isotropic angular distribution in the center-of-mass system with a library of 107 nuclide decay alpha-particle spectra, 24 sets of measured and/or evaluated (alpha,n) cross sections and product nuclide level branching fractions, and functional alpha-particle stopping cross sections for Z<106. The delayed neutron spectra are taken from an evaluated library of 105 precursors. The code provides the magnitude and spectra, if desired, of the resultant neutron source in addition to an analysis of the contributions by each nuclide in the problem.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME

Run times vary based on problem specifications. All 15 test cases ran in ~3 minutes under Redhat Linux Version 6.1 on 450 MHz Pentium III with g77.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0661/03 09-OCT-2002 Masterfiled Arrived
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10. REFERENCES

W. B. Wilson, R. T. Perry, W. S. Charlton, T. A. Parish, G. P. Estes, T. H. Brown, E. D. Arthur, M. Bozoian, T. R. England, D. G. Madland, J. E. Stewart, "SOURCES 4A: A Code for Calculating (,n) Spontaneous Fission, and Delayed Neutron Sources and Spectra," LA-13639 (September 1999). This file will be expanded to the sources4c/docs subdirectory.

R. T. Perry, W. B. Wilson, W. S. Charlton, "Sources-3A: A Code for Calculating (a,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra," Proceedings of the 1998 American Nuclear Society Topical Meeting on Radiation Protection and Shielding (April 19-23, 1998) Volume 2, pp.348-355.

W. S. Charlton, R. T. Perry and W. B. Wilson, "Benchmarking of the Los Alamos Neutron Production Rate Code Sources-3A," Nuclear Instruments and Methods in Physics Research B, 140, pp 1-9 (1999).

W. S. Charlton, R. T. Perry, G. P. Estes, and T. A. Parish, "Derivation and Implementation of the Three Region Problem in the SOURCES Code System," Proceedings 9th International Conference on Radiation Shielding (Tsukuba, Japan, October 17-22, 1999).
CCC-0661/03, included references:
- E. F. Shores:
SOURCES 4C: A Code for Calculating (,n), Spontaneous Fission,
and Delayed Neutron Sources and Spectra,
LA-UR-02-1839 (April 2002) with the following report as Appendix D:
Neutron Production from (,n) Reactions and Spontaneous Fission in ThO2,
UO2, and (U,Pu)O2 Fuels," by R. T.Perry, W. B. Wilson, LA-8869-MS (June 1981).
- E. F. Shores:
Data Updates for the SOURCES-4A Computer Code," LA-UR-00-5016 (2000).
- E. F. Shores:
Present State of the Sources Computer Code," LA-UR-02-709 (Feb 2002).
- E. F. Shores:
Modification of the Three-Region Problem in the SOURCES Code System
LA-UR-02-1617 (2002).
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11. HARDWARE REQUIREMENTS

SOURCES-4C runs on many computers including Personal Computers running either Windows or Linux and Sun SparcStations. A Windows-based LASTCALL executable is included for PC users.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0661/03 FORTRAN-77
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13. SOFTWARE REQUIREMENTS

Intel Pentium and Sun. Executables are included for Windows and for Linux. All other computers require a Fortran compiler. An executable compiled using Compaq Visual Fortran Standard Edition Version 6.6.0 on a PC running Microsoft's Windows 2000 Professional (Version 5.0, Build 2195, Service Pack 2) is included. This executable was also tested in a DOS window of WindowsXP. An executable created under RedHat Linux 6.1 on an Intel PC with Portland Group Inc. V3.3-2 compiler is also included. SOURCES4C was also tested on Sun SparcStation under SunOS 5.6 with g77 0.5.23. LASTCALL is written in Fortran and was compiled under Windows with Compaq Visiual Fortran. The SOURCES4C source file is included; however, no source is provided for LASTCALL; and no Unix version of LASTCALL is available.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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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:
                 Los Alamos National Laboratory
                 Los Alamos, New Mexico, U. S. A.

                 Texas A&M University
                 College Station, Texas, U. S. A.
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16. MATERIAL AVAILABLE
CCC-0661/03
661MNYCP.TXT List of files
C661.PDF Documentation
README.RSI Rsicc readme file
Docs dir. LANL reports
15 test case directories
lastcall.exe LASTCALL Windows executable
Readme4c.txt  Installation and info file
runall.bat   execute all tests under Windows
runone.bat  execute one test case on Windows
run_all   Unix script for all tests
run_one   Unix script for one test case
sources4c.exe   Windows executable
sources4c.for   source for all computers
Input data files
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: alpha spectra, delayed neutrons, fission spectra, isotopes, neutron spectra, radioactive waste storage.