The Nuclear Physics Institute (NPI) of the Czech Academy of Sciences (CAS) operates, among other facilities, a Tandetron linear accelerator, TR-24 and U-120M cyclotrons, and an MT25 microtron. A new accelerator mass spectrometry (AMS) instrument, MILEA, has recently been acquired. Except for the MT25, all facilities are synergic parts of the Centre of Accelerators and Nuclear Analytical Methods Research Infrastructure (CANAM RI) ( http://canam.ujf.cas.cz ). This paper demonstrates the instrumental, scientific and application capabilities of the devices for many fundamental nuclear physics experiments and a wide spectrum of applications. The Tandetron Laboratory has a full arsenal of ion-beam analytical methods, ion-beam nano- and microstructuring techniques, as well as tools for the doping and synthesis of new progressive materials using energetic ion beams. It uniquely utilises ion beams for 3D elemental mapping; it studies internal morphology using ion-microprobe methods applicable in many scientific branches. The TR-24 and U-120M cyclotrons provide the primary beams of accelerated ions as well as the generated secondary fast neutrons, including the necessary instrumentation and the target technology, and enable fundamental experiments in nuclear physics, astrophysics, dosimetry, etc. The microtron MT25 is a source of relativistic electrons (the primary electron beam), the secondary photon beam (bremsstrahlung) and neutrons from photonuclear reactions which are used, e.g. for analysis and preservation of cultural heritage. The MILEA AMS system offers a highly sensitive isotopic ratio measurement of very long-lived radionuclides at levels up to 10–15.

Numerous domains, in fundamental research as well as in applications, require the study of reactions induced by neutrons with energies from few MeV up to few tens of MeV. Reliable measurements also are necessary to improve the evaluated databases used by nuclear transport codes. This energy range covers a large number of topics like transmutation of nuclear waste, design of future fission and fusion reactors, nuclear medicine or test and development of new detectors. A new facility called Neutrons For Science (NFS) is being built for this purpose on the GANIL site at Caen (France). NFS is composed of a pulsed neutron beam for time-of-flight facility as well as irradiation stations for cross-section measurements. Neutrons will be produced by the interaction of deuteron and proton beams, delivered by the SPIRAL-2 linear accelerator, with thick or thin converters made of beryllium or lithium. Continuous and quasi-mono-energetic spectra will be available at NFS up to 40 MeV. In this fast energy region, the neutron flux is expected to be up to 2 orders of magnitude higher than at other existing time-of-flight facilities. In addition, irradiation stations for neutron-, proton-and deuteron-induced reactions will allow performing cross-section measurements by the activation technique. After a description of the facility and its characteristics, the experiments to be performed in the short and medium term will be presented.

The cyclotron driven fast quasi-monoenergetic neutron source based on the p+ 9Be (thin target) reaction was studied at the proton energy around 30 MeV Due to higher melting point of Be, the p+ 9Be(thin), reaction could be considered as an alternative to the most used p+Li(thin) neutron source, providing a similar quasi-monoenergetic neutron spectrum at significantly higher neutron output owing to advance in higher incident proton beam current. The neutron spectrum measured by the time-of-flight method agrees with other experimental data and indicates dominant contribution of ground and first excited states leading to only two peaks, separated by some 2–3 MeV, in the p+thin 9Be neutron spectrum.

Au, Bi, Co and Nb samples were irradiated several times with quasi-monoenergetic neutrons from p + 7Li reaction in the energy range of 18–36 MeV. The activities of the samples were measured with the HPGe detector and the reaction rates were calculated. The cross-sections were extracted using the SAND-II method with the reference cross-sections from the EAF-2010 database. The uncertainties of the final results are discussed.

The thick target neutron field of source reaction p + Be was investigated for a proton energy of 35 MeV. The spectral neutron flux at 0 degrees for two target-to-sample distances was determined by using the dosimetry foils activation method. The present p(35)-Be white neutron spectra provide the suitable basis for irradiation experiments and integral tests of nuclear data.

The activation cross sections for production of Cr-51, Mn-52,Mn-54,Mn-56, Fe-59, and Co-55,Co-56,Co-57,Co-58 radioisotopes in deuteron-induced reactions on natural Fe were measured at deuteron energies up to 20 MeV. Then, within an extended analysis of deuteron interactions with Fe-nat, all processes from elastic scattering until the evaporation from fully equilibrated compound system have been taken into account. Following the available elastic-scattering data analysis that supports the deuteron optical potential for reaction cross sections calculations, increased attention is paid especially to the breakup (BU) mechanism and direct reactions (DR). The deuteron activation cross-section analysis is completed by consideration of the preequilibrium and compound-nucleus contributions, corrected for decrease of the total reaction cross section due to the leakage of the initial deuteron flux towards BU and DR processes. The overall agreement of the measured data and model calculations validates the description of nuclear mechanisms taken into account, particularly the strong effects of direct interactions that have still not been appropriately considered within previous deuteron activation evaluations.

Irradiation of material with quasi-monoenergetic neutrons with energies up to 35 MeV is routinely used for cross-section measurement. Neutron irradiation, gamma measurement, and cross-section extraction are three steps in obtaining the final cross-section, each of them contributing to the final uncertainty. The nature of the spectra, which consists of the monoenergetic peak and the continuum at lower energies, makes the extraction of the cross-sections a non-trivial problem and different methods of extraction are used. In this paper, we identify the main sources of uncertainties, discuss possible improvements, and address the differences between some commonly used methods of cross-section extraction.

The activation cross sections of (d, p), (d, 2n), (d, 2np + nd + t), (d, 2n alpha), and (d, p alpha) reactions on Nb-93 were measured in the energy range from 1 to 20 MeV using the stacked-foil technique. Then, within a simultaneous analysis of elastic scattering and reaction data, the available elastic-scattering data analysis was carried out in order to obtain the optical potential for reaction cross-section calculations. Particular attention was paid to the description of the breakup mechanism and direct reaction stripping and pick-up, followed by pre-equilibrium and compound-nucleus calculations. The measured cross sections as well as all available deuteron activation data of 93Nb were compared with results of local model calculations carried out using the codes FRESCO and STAPRE-H and both default and particular predictions of the code TALYS-1.4 and TENDL-2012-evaluated data.

This work reports on the current status of neutron sources in the Czech Republic as calibrated and ESA compliant stations for space related applications such as the testing and calibration of neutron detectors and neutron sensitive devices as well as for studies of radiation effects of electric and electronic components. The work was carried out as part of the preparatory accession activities of the Czech Republic with ESA. The goal and one of the tasks is to test and evaluate neutron sensitive devices, both conventional and prototypes, developed at ESA and at the IEAP CTU Prague. The facilities consist of both fast and thermal neutron sources providing testing and absolute calibration of a wide range of neutron detectors. The evaluation and calibration of the sources were carried out in cooperation with the Nuclear Physics Institute, Academy of Sciences of the Czech Republic, the Research Center Rez, and the Czech Metrology Institute in Prague.

An accurate knowledge of the cross section for neutron-induced reactions on Co-59 is of importance clue to use of cobalt as a structural material in fission and fusion reactors, its applicability in neutron dosimetry and for testing theoretical models as well. The thin Co foils (0.25 mm thickness, 99.9% purity, Goodfellow product) were irradiated in the quasi-momoenergetic p-Li neutron field. For the production of the neutron fields, the proton beam from the NPI energy-variable cyclotron U120M at proton energies 19.8, 25.1, 27.6, 30.1, 32.7, 35.0 and 37.4 MeV and thin Li-7 target with carbon stopper were used. The reaction Li-7(p, n) produces the high-energy quasi-monoenergetic neutrons with tail to lower energies. The flux density and neutron spectra were evaluated by MCNPX code using Li-7(p,n) cross section measurement of other authors and including correction to the NPI target layout. The time profile of the neutron source strength during the irradiation was monitored by the proton beam current on the neutron-source target, recorded by a calibrated current-to-frequency converter on a PC. Au foils were used as additional monitors. The foil activity determination was performed by the nuclear spectrometry method employing two calibrated HPGe detectors of 23 and 50% efficiency and of FWHM (Full Width Half Maximum) 1.8 keV at 1.3 MeV for gamma-ray measurement. The reaction rates for (CO)-C-59(n, p) Fe-59, Co-59(n, alpha)Mn-56, Co-59(n, 2n alpha)Mn-54, Co-59(n, 3n)Co-57, Co-59(n, 2n)Co-58m and Co-59(n, 2n)Co-58g were obtained. Integral activation cross sections were estimated. The preliminary results are discussed.

The activation cross sections of (d,p), (d,2n), (d,3n), and (d,2p) reactions on 63,65Cu were measured in the energy range from 4 to 20 MeV using the stacked-foils technique. Then, following the available elastic-scattering data analysis that provided the optical potential for reaction cross sections calculations, an increased effort has been devoted to the breakup mechanism, the direct reaction stripping, and the pre-equilibrium and compound-nucleus cross section calculations, corrected for the breakup and stripping decrease of the total reaction cross section. The overall agreement between the measured and calculated deuteron activation cross sections proves the correctness of the nuclear mechanisms account, next to the simultaneous analysis of the elastic-scattering and reaction data.

The cyclotron-based fast neutron source at NPI produces mono-energetic neutron fields up to 35 MeV neutron energy using the p + 7Li(carbon backing) reactions. To be applied for activation cross-section measurements, not only the intensity of neutron peak, but also the contribution of low-energy continuum in the spectra must be well determined. Simulations of the spectral flux from present source at a position of irradiated samples were performed using CYRIC TOF-data validated in the present work against LA150h by calculations with the transport Monte Carlo code MCNPX.Simulated spectra were tested by absolute measurements using a proton-recoil telescope technique. The recoil-proton spectrometer consisted of a shielded scattering chamber with polyethylene and carbon radiators and the Delta E1-Delta E2-E telescope of silicon-surface detectors located to the neutron beam axis at 45 degrees in the laboratory system. Si-detectors were handled by usual data acquisition system. Dead-time and pulse-overlap losses of events were determined from the count rate of pulse generator registered during duty cycle of accelerator operation. The proton beam charge and data were taken in the list mode for later replay and analysis.The calculations for Li-7(p,n) and C-12(p,n) reactions reasonably reproduce CYRIC TOF neutron source spectra. The influence of neutron source set-up (proton beam dimensions, Li-7-foil, carbon stopper, cooling medium, target support/chamber and the geometry-arrangement of irradiated sample) on the spectral flux is discussed in details.

The activation cross sections of (d,p), (d,2n), (d,3n), and (d,2p) reactions on {sup 63,65}Cu were measured in the energy range from 4 to 20 MeV using the stacked-foil technique. Then, following the available elastic-scattering data analysis that provided the optical potential for reaction cross-section calculations, an increased effort was devoted to the breakup mechanism, direct reaction stripping, and pre-equilibrium and compound-nucleus cross-section calculations, corrected for the breakup and stripping decrease of the total reaction cross section. The overall agreement between the measured and calculated deuteron activation cross sections proves the correctness of the nuclear mechanism account, next to the simultaneous analysis of the elastic-scattering and reaction data.

In this work we report the application of the ANC method for the determination of the non-resonant radiative capture amplitude for the important astrophysical CNO cycle reaction 15N(p, γ) 16O, which provides a leak from the CN cycle into the CNO bi-cycle and CNO tri-cycle. It is contributed by the resonance capture to the ground state through two strong 1− resonances and non-resonant capture to the ground state, which interferes with the resonant capture terms. To determine more accurately the contribution from the non-resonant capture we determined the proton ANCs for the ground and seven excited states of 16O by measuring the angular distributions of the peripheral 15N(3He, d)16O proton transfer reaction. Using these ANCs and proton and α resonance widths determined from an R-matrix fit to the data from the 15N(p, α)12C reaction, we calculated the astrophysical S factor for the 15N(p, γ)16O reaction. The results indicate that the direct capture contribution was previously overestimated. We find the astrophysical factor to be S(0) = 36.0 ± 6.0 keVb, which is about a factor of two lower than the presently accepted value. We conclude that for every 2200 ± 300 cycles of the main CN cycle one CN catalyst is lost due to this reaction.

The proton and deuteron induced reactions have a great interest for the assessment of induced radioactivity of accelerator components. Such data are needed for estimation of the potential radiation hazard from the accelerating cavities and beam transport elements. Continuing previous irradiation experiments on copper, we provided two short run to obtain cross-section data for 65Cu(d, p)66Cu reaction. We carried out irradiation experiments with the variable-energy cyclotron U-120M of the Nuclear Physics Institute Řež. The stacked-foil technique was utilized. Because of a relatively short half life (T1/2 = 5, 120 min) and a strong annihilation peak, we placed the 1 cm Pb plate between the irradiated sample and the gamma-ray detector to reduce the dead time. The absolute values of cross-sections were calculated from the induced activities measured by the calibrated HPGe detector. The comparison of present results with data of other authors and prediction of different libraries and model calculation is discussed.

The reaction of protons on 7Li target produces the high-energy quasi- monoenergetic neutron spectrum with the tail to lower energies. Proton energies of 19.8, 25.1, 27.6, 30.1, 32.6, 35.0 and 37.4 MeV were used to obtain quasi-monoenergetic neutrons with energies of 18, 21.6, 24.8, 27.6, 30.3, 32.9 and 35.6 MeV, respectively. Nb cross-section data for neutron energies higher than 22.5 MeV do not exist in the literature. Nb is the important material for fusion applications (IFMIF) as well. The variable-energy proton beam of NPI cyclotron is utilized for the production of neutron field using thin lithium target. The carbon backing serves as the beam stopper. The system permits to produce neutron flux density about 109 n/cm2/s in peak at 30 MeV neutron energy. The niobium foils of 15 mm in diameter and approx. 0.75 g weight were activated. The nuclear spectroscopy methods with HPGe detector technique were used to obtain the activities of produced isotopes. The large set of neutron energies used in the experiment allows us to make the complex study of the cross-section values. The reactions (n,2n), (n,3n), (n,4n), (n,He3), (n,α) and (n,2nα) are studied. The cross-sections data of the (n,4n) and (n,2nα) are obtained for the first time. The cross-sections of (n,2n) and (n,α) reactions for higher neutron energies are strongly influenced by low energy tail of neutron spectra. This effect is discussed. The results are compared with the EAF-2007 library.

The activation cross sections of (d, p), (d, 2p), and (d, p alpha) reactions on Al-27 were measured in the energy range from 4 to 20 MeV using the stacked-foils technique. Following a previous extended analysis of elastic scattering, breakup, and direct reaction of deuterons on Al-27, for energies from 3 to 60 MeV, the preequilibrium and statistical emissions are considered in the same energy range. Finally, all deuteron-induced reactions on Al-27 including the present data measured up to 20 MeV deuteron energy are properly described due to a simultaneous analysis of the elastic scattering and reaction data.

The dosimetry activation foil technique was used for the determination of a white neutron spectrum at the UI20M cyclotron facility of NPUReZ. The neutrons were produced by 37 MeV protons slowing down in the thick heavy water target and have an energy distribution extending up to 37 MeV. To cover the whole energy range a set of 10 foils AI, Ti, Fe, Co, Ni, Y, Nb, In, Lu, and Au was used. The y-rays ITom the decaying nuclei produced in 26 activation reactions were detected. The cross sections for these reaction were chosen ITom European Activation File EAF2007 (up to 55 MeV) after intercomparison with the dosimetry cross section library IRDF-2002 which represents the cross section only up to 20 MeV and other high energy libraries. For the spectrum determination the SAND-II code was used after it had been modified to input dosimetry cross sections above 20 MeV in an arbitrary group structure. The guessed neutron spectrum which is needed to start an adjustment procedure was combined ITom those measured and calculated by the MCNPX code. The uncertainty of the adjusted neutron spectrum was estimated using the uncertainties of measured specific y-activities induced in nuclides and dosimetry cross sections. It is less than 10% in the energy range below 25 MeV, the sensitivity domain of the most dosimetry reactions, but increases above this energy.

The proton and deuteron induced reaction have a great interest for the assessment of induced radioactivity of accelerator components. The IFMIF (International Fusion Material Irradiation Facility) accelerator needs such a data for estimation of the potential radiation hazards from the accelerating cavities and beam transport elements (Al, Cu, Fe, Cr, Nb). The cross sections are needed in the energy range from the threshold (2-10 MeV) up to 40 MeV both for deuterons and protons. In order to investigate the first important nuclides relevant to the IFMIF, we have carried out the irradiation experiment with the variable-energy cyclotron U-120M of the Nuclear Physics Institute Rez. The production cross section of the nuclides 28-Al, 27-Mg, 24-Na from reaction on 27-Al, further - the nuclides 64-Cu, 63-Zn, 62-Zn from reactions on 63-Cu and the nuclides 65-Zn, 65-Ni from reactions on 65-Cu were investigated by irradiation of aluminium and cuprum (natural isotope abundance) foil by deuteron beam of 20 MeV energy. The stacked-foil technique was utilized. The absolute values of cross sections were calculated from the induced activities measured by calibrated HPGe detectors. The gamma-rays from the irradiated foils were analyzed by the DEIMOS code. The comparison of present results with data of other authors and with the prediction of different libraries is discussed.

For validating activation cross-section data in the energy range relevant to IFMIF (International Fusion Material Irradiation Facility), the fast neutron sources were developed utilizing the NPI variable-energy cyclotron U-120M. Novel concept of source reaction was investigated for a generation of the white - (IFMIF-like) - spectrum on NPI cyclotron. The deuteron break-up process induced by 37MeV protons onflowing heavy water target was found to produce neutrons with high intensity, mean energy of 14MeV and spectrum extending to 32MeV. The small-size samples (diameter of 15mm) are irradiated at neutron flux up to 10 11 n/cm 2 /s in this source. The quasi-monoenergetic neutron field in the energy range from 20 to 35MeV is produced using standard 7 Li(p,n) reaction on thin (carbon backed) lithium foil. The p-Li source produces neutron flux up to 10 9 n/cm 2 /s. The present work deals with methodical, technical and functional characteristics of p-D2O and p- 7 Li neutron sources. The determination of spectral flux at position of irradiated samples is described in details. A summary of present and next program of experiments is outlined.