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The paper presents the measured cumulative yields of 44 Ti for nat Cr, 56 Fe, nat Ni and 93 Nb samples irradiated by protons at the energy range 0.04–2.6 GeV. The obtained excitation functions are compared with calculations of the well-known codes: ISABEL, Bertini, INCL4.2+ABLA, INCL4.5+ABLA07, PHITS, CASCADE07 and CEM03.02. The predictive power of these codes regarding the studied nuclides is analyzed.

The paper presents the 207Bi production cross-sections measured by the direct gamma-spectrometry technique in the samples of lead enriched with isotopes 208, 207 and 206, as well as in the samples of natural lead and bismuth, irradiated by protons of 11 energies in the range from 0.04 to 2.6 GeV. The obtained experimental results are compared with the previous measurements, with the TENDL-2019 data-library evaluations and the simulated data by means of the high-energy transport codes MCNP6.1 (CEM03.03), PHITS (INCL4.6/GEM), and Geant4 (INCL++/ABLA). The observed discrepancies between model predictions and experimental data are discussed.

A variant of the target unit based on tungsten rods cooled by molten-salt coolant (alkali-metal fluorides) in a subcritical electronuclear facility is examined. The results of calculations of its main parameters are presented: the neutron yield, neutron spectrum on the lateral surface, top and bottom ends of the target, total energy release, specific energy release and induced activity. The calculations are performed using the three codes MCNPX 2.6B, SHIELD and KATRIN-2.5 and the codes ORIHET3 and DCHAIN-SP for calculating the changes in the radioactivity of the main units. The discrepancies in the parameters of the target unit of a subcritical electronuclear facility were determined by calculating the standard deviation factors. Apparently, the uncertainties in the computational results for the differential and integral parameters are due to the nuclear models and libraries in the programs used.

A proton activation data library for 682 nuclides from 1-H to 210-Po in the energy range from 150 MeV up to 1 GeV was developed. To calculate proton activation data, the MCNPX 2.6.0 and CASCADE/INPE codes were chosen. Different intranuclear cascade, preequilibrium, and equilibrium nuclear reaction models and their combinations were used. The optimum calculation models have been chosen on the basis of statistical correlations for calculated and experimental proton data taken from the EXFOR library of experimental nuclear data. All the data are written in ENDF-6 format. The library is called HEPAD-2008 (High-Energy Proton Activation Data). A revision of IEAF-2005 neutron activation data library has been performed: A set of nuclides for which the cross-section data can be (and were) updated using more modern and improved models is specified, and the corresponding calculations have been made in the present work. The new version of the library is called IEAF-2009. The HEPAD-2008 and IEAF-2009 are merged to the final HEAD-2009 library., 21 pages, 10 tables, 3 figures, only pdf, submitted to Nucl. Instrum. Meth. A

The code CASCADEX representing the merging of intranuclear cascade and evaporation/fission models is discussed. The intranuclear cascade part is extracted from the CASCADE/INPE code. The equilibrium stage of nuclear reactions is described using the Hauser–Feshbach statistical model implemented in the TALYS code. The CASCADEX code has been validated on experimental yields of radionuclides in nuclear reactions induced by protons of energies from 0.8 to 1.2 GeV. The cross-section yields calculated for selected reactions are in a better agreement with experimental data than the results of calculation by INCL4 intranuclear cascade and ABLA evaporation/fission models.

A new evaluated nuclear data library has been created. The library consists of two sub-libraries for neutron and proton incident particles. The neutron sub-library contains nuclear data for transport, heating and shielding applications for 242 nuclides with atomic numbers ranging from 8 to 82 in the energy region of primary neutrons from 10–5 eV to 150 MeV. Data below 20 MeV are taken mainly from ENDF/B-VI (revision 8) and for some nuclides, from the JENDL-3.3 and JEFF-3.0 libraries. The proton sub-library should contain data for the same range of target nuclides and energies. Proton-induced evaluated cross-section files are available for 15 nuclides at the moment. The evaluation of emitted particle energy and angular distributions at energies above 20 MeV (for incident neutrons) and above the reaction threshold (for incident protons) was performed with the help of the ALICE/ASH code and the analysis of available experimental data. The total cross-sections, elastic cross-sections and elastic scattering angular distributions were calculated with the help of the coupled channel model. The results of the calculation were adjusted to the data from ENDF/B-VI, JENDL-3.3, or JEFF-3.0 at the neutron energy equal to 20 MeV. The library is written in ENDF-6 format using the MF=3/MT=5 and MF=6/MT=5 representations.

A new evaluated nuclear data library has been created. The library consists of two sub‐libraries for neutron and proton incident particles. The first version of neutron sub‐library has been completed and described in the present paper. The library contains nuclear data for transport, heating, and shielding applications for 242 nuclides ranging in atomic number from 8 to 82 in the energy region of primary neutrons from 10‐5 eV to 150 MeV. Data below 20 MeV are taken mainly from ENDF/B‐VI (Revision 8) and for some nuclides, from the JENDL‐3.3 and JEFF‐3.0 libraries. The evaluation of emitted particle energy and angular distributions at the energies above 20 MeV was performed with the help of the ALICE/ASH code and the analysis of available experimental data. The total cross sections, elastic cross sections, and elastic scattering angular distributions were calculated with the help of the coupled channel model. The results of the calculation were adjusted to the data from ENDF/B‐VI, JENDL‐3.3m or JEFF‐3.0 at the neutron energy equal to 20 MeV. The library is written in ENDF/B‐VI format using the MF=3/MT=5 and MF=6/MT=5 representations.