last modified: 20-JAN-1997 | catalog | categories | new | search |

IAEA1349 MSM-SOURCE.

MSM-SOURCE, Neutron Source Generator for MCNP from Proton Neutron Interaction

top ]
1. NAME OR DESIGNATION OF PROGRAM:  MSM-SOURCE.
top ]
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
MSM-SOURCE IAEA1349/01 Tested 02-JUN-1998

Machines used:

Package ID Orig. computer Test computer
IAEA1349/01 IBM PC PC Pentium 166
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

The MSM-SOURCE code generates the input data for the MCNP code (for 3b- and 4- versions) [1], simulating the set of single neutron sources (the energy of neutrons is limited by 20 MeV, as required in MCNP code), produced in the sample during the proton transmission. 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 parametrisation [2],[3]) 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
parametrisation is used [3].
top ]
4. METHODS

The method of estimation of double differential spectra and multiplicities of nucleons is completely described in [3]. 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 parametrisation formula [3].
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

MSM-SOURCE code is applicable for the calculations for the
target mass from A=12 to A=238. The MSNP 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
top ]
6. TYPICAL RUNNING TIME

The program produces results for most problems on modern PC's in a matter of seconds.
top ]
7. UNUSUAL FEATURES

As MSM-SOURCE code is the service program for MCNP the output into file "mcnp.inp" organized corresponding to the input requirements of MCNP code (see manual for 3b- and 4- versions of MCNP code) and there is the possibility of direct inclusion of it into the input data to MCNP code.
top ]
8. RELATED OR AUXILIARY PROGRAMS

The code MSM-SOURCE is independent program and generates the input data for the MCNP code (for 3b- and 4- versions).
top ]
9. STATUS
Package ID Status date Status
IAEA1349/01 02-JUN-1998 Tested at NEADB
top ]
10. REFERENCES

[1] W.L. Thomson et.al:
    "MCNP - a general Monte Carlo Code
    for neutron and photon transport",LA-87545-M,(April 13,
    1981)
[2] I.G. Bogatskay et al.:
    Phys.Rev.C22, 1980,p 209.
[3] Eremenko D.O., Fotina O.V. et al:
    Preprint INP MSU 94-8/330, Moscow, 1994;
    Proceedings of the 2-nd Inter. 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-Moulineaux
    (France), 1994, p.287-300;
    Bull.Acad.Sci. RUS, Phys.Ser., 1995, 59, N 11, p.198.
top ]
11. HARDWARE REQUIREMENTS

PC 386 or higher processor is required. The required high speed memory is 63 KB.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1349/01 FORTRAN-77
top ]
13. SOFTWARE REQUIREMENTS

DOS, UNIX. The program can be run under the operating systems, where FORTRAN language is installed.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The code was designed for quick and easy estimations of
basic stopping characteristics of proton transmission, for
generation of input data for the MCNP code (for 3b- and 4-
versions). The results of calculations well reproduce the
experimental data [3].
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

  O.V. Fotina, Yu.L. Parfenova, D.O. Eremenko, S.Yu.Platonov,
  O.A. Yuminov,
  Laboratory of Nuclear Reactions,
  Institute of Nuclear Reactions,
  Moscow State University
  Leninskie Gory
  Moscow 119899
  Russia
top ]
16. MATERIAL AVAILABLE
IAEA1349/01
MSM-Source.f Source code
MSM-INPUT Input file
MSM-OUTPUT Output files
Abstract.txt Program Abstract
top ]
17. CATEGORIES
  • L. Data Preparation

Keywords: data processing, neutron, source.