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[en] The purpose of this paper is to give instruction in the use of the code ALICE for a range of nuclear reaction problems, with emphasis on the direct reactions in the continuum, which are generally referred to by the equivalent terms precompound or preequilibrium. The ALICE code has been designed and maintained to emphasize ease of use by non-experts, high speed, and versatility. It's predictive capabilities have been shown, yet it has not been written to optimize accuracy when this goal conflicts with speed and ease of use. Other codes will be preferable when accuracy (better than ∼80%) is more important than speed. The ALICE code can perform precompound decay calculations, followed by compound nucleus decay, including fission competition. The equilibrium decay channels are calculated using a deterministic method. Nearly all input parameters may be generated internally, so that execution may take place with as little input as target and projectile charge and mass and projectile energy. On the other hand, possibilities exist to override internally determined input values and calculational parameters, if desired, making the code capabilities quite versatile; the user can grow into the codes
[en] Neutron induced fission cross sections of actinides like the Pu-isotopes are of relevance for the development of nuclear transmutation technologies. For 242Pu current uncertainties are of around 21 %, the target uncertainties in the order of 7 %. Sensitivity studies show that the total uncertainty has to be reduced below 5 %, to allow for reliable neutron physics simulations. This challenging task was performed at the neutron time-of-flight facility nELBE at HZDR, Dresden. Improved experimental conditions and beam power, paired with the right spectral shape of the nELBE neutron source provided excellent conditions to achieve this aim. Within the TRAKULA project, large and homogeneous deposits of 235U and 242Pu have been produced successfully. Using them in two consecutively placed fission chambers allows the determination of the neutron induced fission cross section of 242Pu relative to 235U. Experimental results are presented and compared to recent experiments and evaluated data. Corrections addressing the neutron scattering are discussed by using results of different neutron transport simulations (Geant 4, MCNP 6 and FLUKA).
[en] An integrated negative surface ionization target ion source was developed for the Soreq On-Line Isotope Separator, which is especially efficient for bromine and iodine isotopes. In this work 87-90Br and 138-141I were identified by beta activity scans and half-lives of 86-89Br and 137-139I were measured. (H.K.)
[en] Fragment deformation effect on charge distribution at cold fission is considered. Dependence of values of fission barrier, compound-nucleus energy, change distribution and deformations of nuclei-fragments on deformations of nuclei of target and projectile is shown
[en] There is a growing interest for the use of some actinide elements as nuclear fuels. In this paper we predict the total delayed neutron yields as well as the energy components of the delayed activities. This prediction is given for actinide elements which are important in the nuclear energy field, and do not have experimental data