[en] 1 - Description of program or function: The MSM-SOURCE code generates the input data for the MCNP code (for 3b- and 4- versions), 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 parameterization) 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 parameterization is used. 4. Methods - The method of estimation of double differential spectra and multiplicities of nucleons is completely described. The double differential inclusive nucleon spectra form in the next processes: cascade nucleon emission, pre-equilibrium 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 parameterization formula. 3 - 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< Z<93