[en] The description of experimental data for ²³²Th, and ²³⁸U on cross sections-total, radiative captUre, elastic and inelastic scattering - in the 1-1000 keVneutron energy range is obtained in the Hauser-Feshbach-Moldauer formalism. Evaluated average resonance parameters are recommended for using in the evaluated nuclear data files for ²³²Th and ²³⁸U. The accuracy of ²³⁸U radiation capture cross sections in the range of unresolved resonances is 3-5%. The estimated ²³⁸U cross section curve σsub(nγ) (E) in the 40-100 keV neutron energy range is 4-5% lower than the BNAB-MICRO and BNAB-78 estimates; while below 40 keV, it lies between them

[en] Based on the description of fission with Fokker-Planck equation the variance of the Coulomb energy of fragment repulsion for a classical distribution function of a collective variables is calculated with d-like and equilibrium distribution of collective variables at the saddle point. Theoretical data are given for the ²³⁶U nucleUs. It is concluded that the calculated values of the Coulomb energy variance are always less than the results of calculations of this value with equilibrium initial conditions

[en] Activation cross sections for ²³⁷Np(n, γ) ²³⁸Np reaction have been measured at 7 neutron energies between 0.3 abd 2.0 MeV. Neutrons were produced by means of the ³H (p, n)³He reaction using Van de Graaff accelerator. The measurements were made relative capture cross section of ¹⁹⁷Au

[en] The transmission measurement procedure under the self-indication conditions by the neutron scattering on the uranium 238 in the 1-100 keV neutron energy ranqe are described. The experimental values of self-indication functions, average cross section of scattering and the self-indication resonance factors are given

[en] The spectrum of ²⁵²Cf spontanious fission prompt neutrons has been measured in the neutron energy range of 0.01-10 MeV by the time-of-flight method using a fast ionization chamber with ²³⁵U layers as a neutron detector. The experimental data in the 0.01-5 MeV range of neutron energies on the whole agree with the Maxwell distribution to the +-5% accuracy. In the energy range above 5 MeV a systematic deviation of Maxwell distribution is observed

[en] Measurement of fission cross section for ²³⁶U by 5.7-10.7 MeV neutrons have been carried out by the pulse-synchronization method. Measurement accuracy was better than 1.5%. Measurement errors are given. The spread of experimental data according to the cross section ratio of the fission obtained by different groups is equal to 5-7%

[en] Two-level model to calculate transmission functionals and self-shielding factors for fissile nuclides in the unresolved resonance region is presented. To similate quasi-resonance cross section structure, average resonance parameters, statistical parameter distributions and gaussian low order quadratare formulae are employed. Theoretical predictions and experimental data for ²³⁹Pu are compared

[en] For the resonance neutron cross section model simple analytical formulae for Doppler broadening resonances has been obtained. With the help of average in the energetical group parameters one can reproduce cross-section functions necessary for self-shielding evaluation

[en] Calculated fission product (n, γ)-cross-section following uranium and plutonium fission products by thermal and fissjon neutrons is presented for different irradiation duration range and cooling times and integral neutron density. Mean cross section of the whole fission product mixture for an effective nucleus decreases with the growth of irradiation duration. Increase of the neutron flux density only accelerates this process

[en] Absolute measurements of the value α=deltasub(γ)/deltasub(f) on resonances of uranium-235 and plutonium-239 have been made on the basis of multiplicity spectrometry of excited nuclei radiation. The accuracy of obtained α values on most of the resonances is no worse than 2% for uranium-235 and 3% for plutonium-239