Neutron flux determination in the spallation target Quinta

The experiments with a spallation target QUINTA were performed at the Joint Institute for Nuclear Research, Dzelepov Laboratory of Nuclear Problems. The spallation target contains 512 kg of natural uranium divided in five sections. Various types of threshold activation detectors were placed in sandwich form in the whole volume of the target. These detectors were irradiated by the secondary neutron field generated by the 660 MeV proton beam. The detectors were measured and analysed by the gamma-ray spectroscopy. The average neutron flux in different positions of the QUINTA target was calculated. To obtain neutron flux there were calculated cross sections using the TALYS 1.8 code. These cross sections were also compared with the EXFOR experimental data library to ensure their accuracy. The simulated neutron flux was calculated by MCNPX 2.7 using intranuclear cascade model INCL4.2 and de-excitation model ABLA. The results of the experiment together with results of the simulations can be used for the validation of nuclear models. (author)