GNSR - a computer code to calculate response functions of gas-filled neutron detectors

This report describes in detail the capabilities of a program named GNSR (version 1.1), which is designed to calculate response functions and efficiencies of various gas-filled neutron detectors. Included are recoil detectors filled with H_2, "3He, "4He, and mixtures with commonly used quenching gases. A cylindrical detector geometry is assumed. The program calculates the detector response in various neutron beam configurations: point source, isotropic source, parallel beam, extended cylindrical source, and a plane rectangular localized source. Applicability of the program is limited to non relativistic energies; thermal neutrons are excluded as well. Scattering and reactions in the wall or other parts of the detector assembly as well as multiple neutron interactions in the gas are not taken into account in this version of the code. The second part of the report serves as a 'User Manual' giving a detailed description of the various input and output files. In particular, the response matrix is put out in a format suitable for direct input into the HEPRO unfolding package compiled by Matzke. (orig.)Available from TIB Hannover: RO 8345(26) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekSIGLEDEGerman