1. NAME AND TITLE
MSM-SOURCE: Code System for Generation of Input Data for MCNP.
Department of Nuclear Reactions at Moscow State University, Moscow, Russia.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; PC 386 or higher processor, IBM RS/6000 (P00369/MNYCP/00).
4. NATURE OF PROBLEM SOLVED
The MSM-SOURCE code was designed for quick and easy estimations of basic stopping characteristics of proton transmission, for generation of the source definition (SDEF) portion of the input data for MCNP (for 3b- and 4- versions) , simulating the set of single neutron sources, produced in the sample during the proton transmission. It does not generate the ful MCNP input file. The results of calculations well reproduce the experimental data . It permits one to extend the possibilities of the MCNP code for consideration of secondary neutrons from the proton interaction with nuclei of the sample substance. The MSM-SOURCE code is applicable for calculations of the proton transport for the incident energies from 0.1 to 1 GeV and various targets 12 < A < 238.
This code is based of the Moving Source Model (MSM) (using the original parametrization
,) and Bethe stopping theory with the relativistic corrections for protons. It allows the
estimations of the proton range, the changes of the proton current and the neutron production
versus the depth. The double differential spectra and the multiplicities of nucleons, produced in
the primary proton-induced reactions, are obtained. For the evaluation of inelastic cross section
the original parametrization is used .
5. METHOD OF SOLUTION
The method of estimation of double differential spectra and multiplicities of nucleons is
completely described in . The double differential inclusive nucleon spectra form in the next
processes: cascade nucleon emission, preequilibrium emission, and evaporation. The inclusive
nucleon spectra are obtained by summation of the contributions of these processes. The
contribution of each process is estimated using the original parametrization formula .
6. RESTRICTIONS OR LIMITATIONS
MSM-SOURCE code is applicable for the calculations for the target mass from A=12 to
A=238. The MCNP code analyzes transmission of neutrons with energy up to 20 MeV and all
the secondary neutrons from (p,n) reactions with energy above 20 MeV are ignored. The data for
ionization parameters of Bethe stopping theory, used for the description of the proton transport,
are determined in the program for 5<Z<93.
7. TYPICAL RUNNING TIME
The program produces results for most problems on modern PC's in a matter of seconds.
8. COMPUTER HARDWARE REQUIREMENTS
MSM-SOURCE runs on many computers including personal computers and IBM RS/6000.
9. COMPUTER SOFTWARE REQUIREMENTS
The code runs under either DOS or Unix. It has been compiled with Microsoft FORTRAN
5.1, WatCom Fotran, NDP-Fortran, and Lahey compilers on PC. The Lahey Fortran 90 V4.5
compiler was used to create the executable included in the package. A Fortran compiler is
required on Unix systems.
a) Included in documentation:
O. V. Fotina, Yu. L. Parfenova, D.O. Eremenko, S. Yu. Platonov, O. A. Yuminov,
"README.TXT" (May 1998).
b) Background information:
 W.L. Thomson et.al, "MCNP - A General Monte Carlo Code for Neutron and Photon Transport", LA-87545-M,(April 13, 1981)
 I.G. Bogatskay et al., Phys.Rev.C22, 1980,p 209.
 D. O. Eremenko, O. V. Fotina, et al, Preprint INP MSU 94-8/330, Moscow, 1994;
Proceedings of the 2-nd International Seminar on Interaction of Neutrons with Nuclei. Neutron
Spectroscopy, Nuclear Structure, Related Topics. JINR, Dubna, 1994, E3-94-419, p.310-317;
Intermediate energy nuclear Data: Models and codes. Proceedings of a specialists meeting
Issy-les-Moulineax (France), 1994, p.287-300; Bull. Acad. Sci. RUS, Phys. Ser., 1995, 59, N 11,
11. CONTENTS OF CODE PACKAGE
The package includes the referenced document in 10.a and one DS/HD (1.44MB) diskette
written in DOS format which contains the Fortran source, PC executable, and test case input and
12. DATE OF ABSTRACT
KEYWORDS: INPUT GENERATOR; PROTON; MICROCOMPUTER; WORKSTATION