PADF-2. Data for stable isotopes of Ca, Cr, Fe, and Ni

The cross-sections for the interaction of protons with calcium, chromium, iron, and nickel isotopes were obtained at energies from the reaction threshold to 200 MeV. The work included calculations using different models and computer codes, analysis of experimental data, and evaluation of cross sections. For reactions for which no experimental data are available, the cross-sections were estimated by analyzing the calculated data, taking into account the quality and predictive power of various models in different energy ranges. The resulting files can be downloaded from the https://t1p.de/3vzun website

Atomic displacement cross-sections for neutron irradiation of materials from Be to Bi calculated using the arc-dpa model

Displacement cross-sections for an advanced assessment of radiation damage rates were obtained for a number of materials using the arc-dpa model at neutron incident energies from 10−5 eV to 10 GeV. Evaluated data files, CEM03 and ECIS codes, and an approximate approach were applied for the calculation of recoil energy distributions in neutron induced reactions. Three sets of displacement cross-sections based on the use of low-energy data from JEFF-3.3, ENDF/B-VIII.0, and JENDL-4.0u were prepared. Files contain also cross-sections calculated using the standard NRT model. Special efforts were made to estimate the uncertainty of obtained displacement cross-sections

Simulation of heavy cluster emission in nucleon induced reactions on targets from C to Bi at intermediate energies (KIT Scientific Reports ; 7684)

The simulation of heavy cluster emission in nucleon induced reactions was performed using the coalescence model combined with the intranuclear cascade evaporation model and pick-up coalescence model combined with hybrid precompound and evaporation model. Be production cross-sections for neutron and proton induced reactions were calculated for 274 stable targets from C to Bi at primary particle energies up to 200 MeV. The data obtained supplement the content of existing activation data files and can be used for the calculation of Be production rates in nucleon induced reactions at intermediate energies

Reference data for evaluation of gas production cross-sections in proton induced reactions at intermediate energies (KIT Scientific Reports ; 7660)

Proton-, deuteron-, triton-, 3He, and -particle production cross-sections were evaluated for proton induced reactions for 278 stable target nuclei with an atomic number from 3 to 83 for a number of incident proton energies from 62 to 1200 MeV using available experimental data and results of model calculations. Data obtained can be used for the evaluation of gas production cross-sections at intermediate incident proton energies. An example of the use of the data is given for 9Be(p,x) reactions

Evaluated activation cross section data for proton induced nuclear reactions on W up to 3 GeV incidence energy (KIT Scientific Reports ; 7628)

Evaluated cross-section data files were prepared for the stable tungsten isotopes to provide reliable and sound nuclear data for activation and inventory calculations of the European Spallation Source (ESS) which utilizes a tungsten target. The data files contain yields of radionuclides produced by proton induced reactions with incident energies up to 3 GeV. The data were obtained from the analysis of calculations using advanced nuclear models, available experimental data and systematics

Evaluated data files for n+ 180^{180}W and 183^{183}W irradiation at incident neutron energies up to 200 MeV

New evaluation of nuclear data was performed for tungsten isotopes $^{180}$W and $^{183}$W at incident neutron energies up to 200 MeV. Calculations were carried out using aspecial version of the TALYS code implementing the geometry dependent hybridmodel and models for the non-equilibrium light cluster emission.The evaluation was performed using the results of calculations, availablemeasured data, systematics predictions, and covariance information. The TEFALcode and the FOX code from the BEKED package were applied for the formatting ofthe data

Evaluated displacement and gas production cross-sections for materials irradiated with intermediate energy nucleons

International Conference on Nuclear Data for Science and Technology (ND) -- SEP 11-16, 2016 -- Bruges, BELGIUMWOS: 000426429500034Atomic displacement and gas production cross-sections were obtained for a number of materials to calculate radiation damage and gas production rate in nuclear-and fusion reactors, and neutron spallation sources. An advanced atomistic modelling approach was applied for calculations of the number of stable displacements in materials.Fusion for Energy [F4E-GRT-168.01, F4E-GRT-168.02]The work leading to this publication has been funded partially by Fusion for Energy under the Specific Grant Agreements F4E-GRT-168.01 and F4E-GRT-168.02. This publication reflects the views only of the authors, and Fusion for Energy cannot be held responsible for any use which may be made of the information contained therein

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $^{235}$U, $^{238}$U and $^{239}$Pu, on $^{241}$Am and $^{23}$Na, $^{59}$Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy