[en] The differential neutron and proton production cross sections have been investigated for 200 MeV incident deuterons on thin and thick ⁹Be, ⁵⁶Fe and ²³⁸U targets using the LAHET code system. The examples of the deuteron beam on different target materials are analysed to determine the differences of converting the energy of the beam into the nucleons produced. Both double differential, energy and angle integrated nuclear production cross sections are presented together with the average nucleon multiplicities per incident deuteron. (K.A.)

[en] Both cross section measurements and various applications could be realised successfully using the high energy neutrons that will be produced at SPIRAL-2. Two particular cases were examined in more detail, namely: (a) neutron time-of-flight (nToF) measurements with pulsed neutron beams, and (b) material activation-irradiation with high-energy high-intensity neutron fluxes. Thanks to the high energy and high intensity neutron flux available, SPIRAL-2 offers a unique opportunity for material irradiations both for fission and fusion related research, tests of various detection systems and of resistance of electronics components to irradiations, etc. SPIRAL-2 also could be considered as an intermediate step towards new generation dedicated irradiation facilities as IFMIF previewed only beyond 2015. Equally, the interval from 0.1 MeV to 40 MeV for neutron cross section measurements is an energy range that is of particular importance for energy applications, notably accelerator driven systems (ADS) and Gen-IV fast reactors, as well as for fusion related devices. It is also the region where pre-equilibrium approaches are often used to link the low (evaporation) and high energy (intra-nuclear cascade) reaction models. With very intense neutron beams of SPIRAL-2 measurements of very low mass (often radioactive) targets and small cross sections become feasible in short experimental campaigns. Production of radioactive targets for dedicated physics experiments is also an attractive feature of SPIRAL-2. In brief, it was shown that SPIRAL-2 has got a remarkable potential for neutron based research both for fundamental physics and various applications. In addition, in the neutron energy range from a few MeV to, say, 35 MeV this research would have a leading position for the next 10-15 years if compared to other neutron facilities in operation or under construction worldwide. (author)

[en] An efficient way to produce the neutron-rich nuclei in the mass range of 70< A<170 may be achieved via neutron induced fission in uranium ²³⁸U. Depending on the incident neutron energy, the target size and its constituents, it might be also possible to increase this production rate by the secondary neutrons from primary fissions. A few different methods for producing neutrons and their induced fissions following the Be(d,xn) reactions are investigated within the SPIRAL Phase-II project at GANIL. Density, size and material contents of the production target as well as energy of the incident deuteron beam are the major parameters of interest. The production of neutron-rich isotopes presented seems to be very promising if compared to already existing or planned different RIB facilities. (author)

[en] The revival of interest for production of neutrons by light projectiles has been recently renewed because they are the basis in the development of powerful neutron sources for various applications like nuclear energy production and incineration of nuclear waste, material structure analysis, tritium production, etc. Another interest is related to the possibility of the production of radioactive ion beams (RIB) by neutron induced fission. One of the most important tasks in this context is to determine the most efficient way to convert the primary beam energy into neutrons produced afterwards. The problem is investigated by varying the incident energy of different projectiles for different target materials and assemblies. Consequently, a few direct applications of our investigations are presented and compared with experimental data or other theoretical estimations. (author)

[en] This document presents cross-section calculations up to 130 MeV for Pu²³⁹ using the Talys-0.64 code. The photoabsorption process is described by the giant dipole resonance and quasi-deuteron mechanisms. Preequilibrium particle emission is treated with the classical exciton model. At equilibrium, the compound nucleus decay channels are handled within the Hauser-Feshbach statistical model. Neutron transmission coefficients are calculated with a double humped parabolic model. A few sensitive nuclear parameters were fine-tuned to better reproduce the experimental data available for (γ,n), (γ,2n) and (γ,f) partial cross-sections. In addition, the nuclear models provide predictions of the emitted neutron energy and angular distributions. (A.C.)

[en] This report presents cross-sections calculation up to 130 MeV for U²³⁵. The photoabsorption process is described by the giant dipole resonance and quasi deuteron mechanisms. Neutron emission is treated within the preequilibrium and statistical models while fission is also calculated within this statistical approach using a double-humped fission barrier. The U²³⁵(γ,n), (γ,2n) and (γ,f) cross-sections are calculated with the TALYS-0.64 code using a coupled channels optical potential. Charges in level densities did not affect results significantly. Fission barrier heights and widths were modified to reproduce experimental data. Neither fission level densities nor other default fission parameters were changed. More calculations are needed in order to check cross-sections sensitivity to other level densities and fission models. (A.C.)

[en] The predictions of neutron production induced by deuterons and protons with the LAHET code system are presented and compared. The incident energy of the projectiles, averaged neutron multiplicities, angular and energy distributions of emitted neutrons from different target materials and their further multiplication in the multiplying medium are considered as the most important parameters of our interest. The energy gain in the simplified sub-critical target assembly is estimated and compared for both of the incident particles as a function of their kinetic energy. (K.A.)

[en] We have used MCNPX coupled to CINDER to estimate the production of radioactive nuclides in the EURISOL 4 MW liquid mercury target during a 40 years'lifetime of the installation. The calculations have been done with different intra-nuclear cascade and fission evaporation model combinations. A benchmark exercise has allowed a better understanding of differences seen between these models for the creation of tritium and fission products. To obtain a realistic production yield for tritium gas in proton induced spallation reactions, we recommend using the ISABEL-RAL model, while both CEM2k and BERTINI-RAL overestimate the production rate above 1 GeV incident proton. The best combinations of models to calculate the residual nuclei production are those using ABLA fission-evaporation model, CEM2k or combinations using RAL model are giving too broad mass distributions when compared to available data. An extensive list of radio-nuclides was obtained and is available on tabular format, we show that the 4 nuclei whose contributions to the total activity of the mercury target (after 40 years of irradiation) are the most important are the following: -) 1 day after shutdown: Y⁹¹ (15%), Y⁹⁰ (13%), Hg¹⁹⁷ (6%) and Sr⁸⁹ (5%); -) 1 year after shutdown: H³ (19%), Y⁹⁰ (17%), Sr⁹⁰ (17%) and Nb^93* (10%); -) 10 years after shutdown: Y⁹⁰ (22%), Sr⁹⁰ (22%), H³ (18%) and Nb^93* (14%); and -) 100 years after shutdown: Mo⁹³ (34%), Nb^93* (32%), Pt¹⁹³ (9%) and Y⁹⁰ (8%). (A.C.)

[en] This document describes the method used to compute the activation of the structure components near the electron-positron converter of the Lure accelerator (Orsay). Activation comes from photon and neutron reactions on nuclei belonging to the concrete structure. Only radio-nuclides with a half-life greater than 200 days are considered penalizing for dismantling operations. The main photonuclear reactions produce the following nuclides: Na²², Cl³⁶, Mn⁵⁴, Nb⁹², Ba¹³³, Co⁵⁷ and Co⁶⁰. The main neutron reaction generate the following nuclides: H³, C¹⁴, Cl³⁶, K⁴⁰, Co⁶⁰, Ni⁶³, Zn⁶⁵, Se⁷⁹, Zr⁹³, Ag¹⁰⁸, Ag¹¹⁰, Ba¹³³, Cs¹³⁴, Eu¹⁵², Eu¹⁵⁴, Fe⁵⁵, Ca⁴¹, Na²², Mn⁵⁴, Cs¹³⁷, Nb⁹² and Ti²⁰⁴. The MCNPX code has been used to compute the values of the photon and neutron fluxes received by the structure components, the activation has been computed with the Cinder code from the flux values. The main contributors for radioactivity on long term basis appear to be Ca⁴¹ and Ni⁶³. Calculations have been compared with the measurement of activities of 3 concrete samples drilled out from the structure. The results of the comparison are given for Co⁶⁰, Cs¹³⁴, Eu¹⁵² and Eu¹⁵⁴. The computed values appear to be greater by a factor varying from 2 to 5 which is consistent with the method used that naturally overestimates the activation. These results are considered as satisfactory for performing waste zone labelling. (A.C.)

[en] The revival of interest for production of neutrons by light projectiles has been recently renewed because they are the basis in the development of powerful neutron sources for various applications like nuclear energy production and incineration of nuclear waste, material structure analysis, tritium production, etc. Another interest is related to the possibility of the production of radioactive ion beams (RIB) by neutron induced fission. One of the most important tasks in this context is to determine the most efficient way to convert the primary beam energy into neutrons produced afterwards. The problem is investigated by varying the incident energy of different projectiles for different target materials and assemblies. Consequently, a few direct applications of our investigations are presented and compared with experimental data or other theoretical estimations. (author)