[en] By application of a lead-neutron-multiplier in the blanket of a fusion reactor, containing no fission material, the neutron intensity and thus the tritium yield can be enhanced. For a precise determination of the neutron constants of lead, in the case of which neutron multiplication is effected by the (n,2,n)-reaction, it is of interest to study the neutron spectrum behind the lead layer, using neutron generators as a neutron source. (orig./RW)

[en] This report tackles the problems of the ⁸²Sr cyclotron production using a ⁸²Sr-⁸²Rb generator. ⁸²Sr was obtained from a RbCl (99% ⁸⁵Rb) target using the ⁸⁵Rb(p,4n) reaction with 70 MeV protons at the current up to 75μA. Chemical processing included chromatographic isolation of Sr in an ion exchange column. (author). 3 refs.; 1 tab

[en] A new generation transport in TNR is characterized by substantially higher level of requirements on the accuracy of cross-sections (1--3% for total and 10--20% for double differential ones). This is true in the first place for the breeder and coolant materials in the blanket as well as for shielding materials. However, the experience of integral experiments calculation analysis convinces that the increase in accuracy of single microscopic data ensures not always in achievement of sufficient accuracy of single microscopic data ensures not always in achievement of sufficient accuracy in an integral result in the calculation with concrete nuclide data. The natural criterion of the data quality is an integral experiment which enables for the data producer to obtain information on advantages and disadvantages of a file, and for the user -- to determine the level of confidence in his calculation results. This paper provides a short review of experimental and calculated works on testing neutronic data for neutron multiplying materials, such as ²³⁸U, Th, Be and Pb

[en] This paper is devoted to a comparison of the experimental and calculated leakage neutron spectra and total neutron leakages from U, Th, Pb and Be spherical assemblies and also to a comparison of experimental and calculated reaction rates in U and Th assemblies. It was shown that the calculation with ENDF/B-IV data describes the shape of the neutron spectrum better for all considered materials. The full multiplication of neutrons for the U assembly is reproduced more accurately by the calculation with ENDL-75 data, and for Th, Be and Pb assemblies, by the calculation with ENDF/B-IV data. (orig.)

[en] Status of the neutron data for natural iron is considered. Main results of the experiment with dron sphere 7.5 cm of thickness shell and a central 14 MeV neutron source are briefly discribed. (orig.)

[en] The leakage neutron spectra from metallic spheres were measured on the 14 MeV pulsed neutron generator of the Physics and Power Engineering Institute. The experiment was performed by the time-of-flight method. The experimental set-up and the methods of conducting the measurements and treating the results are described. The experimental data are compared with calculations performed with the BLANK program, using ENDF, ENDL, JENDL and BROND evaluated data files. (author). 7 refs, 6 figs, 3 tabs