1. NAME AND TITLE
SOURCES-4C: Code System For Calculating alpha,n; Spontaneous Fission; and Delayed Neutron Sources and Spectra.
Los Alamos National Laboratory, Los Alamos, New Mexico.
Texas A&M University, College Station, Texas.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; PC and Sun (C00661MNYCP04).
4. NATURE OF PROBLEM SOLVED
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.
5. METHOD OF SOLUTION
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.
6. RESTRICTIONS OR LIMITATIONS
7. 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.
8. COMPUTER 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.
9. COMPUTER SOFTWARE REQUIREMENTS
At RSICC the code was tested on 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.
The Adobe Acrobat Reader freeware is available from http://www.adobe.com to read and print the electronic documentation.
a. included documentation in electronic format on the CD in file DOC/C661DOC.PDF:
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).
b. background 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).
11. CONTENTS OF CODE PACKAGE
The package is transmitted on a CD which includes the electronic documents in 10.a and the SOURCES4C Fortran source, PC executables, data libraries, and test cases in a self-extracting compressed Windows file. The Linux/Unix version is transmitted in a GNU compressed tar file on the same CD.
12. DATE OF ABSTRACT
June 1998, revised May 2000, August 2001, March 2002, July 2002.
KEYWORDS: ISOTOPE INVENTORY; NEUTRON; WASTE MANAGEMENT; MICROCOMPUTER; WORKSTATION