Development of SCINFUL-CG code to calculate response functions of scintillatiors with various shapes used for neutron measurement

Endo, Akira   ; Kim, E.; Yamaguchi, Yasuhiro

SCINFUL has been used to calculate response functions of organic scintillators for high-energy neutron spectroscopy. However, the applicability of SCINFUL is limited to the calculations for cylindrical NE213 and NE110 scintillators. In the present study, SCINFUL-CG was developed by introducing a geometry specifying function and high-energy neutron cross-section data into SCINFUL. The geometry package MARS-CG, the extended version of the CG (Combinatorial Geometry), was programmed into SCINFUL-CG to express various geometries of detectors. Neutron spectra in the regions specified by the CG can be evaluated by the track length estimator. The cross section data of silicon, oxygen and aluminum for neutron transport calculation were incorporated up to 100MeV using the data of LA150. Validity of SCINFUL-CG was examined by comparing calculated results with those by SCINFUL and MCNP and experimental data. SCINFUL-CG can be used for the designs of high-energy neutron spectrometers and neutron monitors using the organic scintillators. The present report is a user's manual of SCINFUL-CG.