[en] Numerical experiences are made to investigate non trivial solutions, for t→∞, of a parabolic nonlinear problem, with initial and boundary conditions, and verify the concordance with the corresponding nonlinear elliptic (or stationary) problem. The model studied belongs to nonlinear diffusion problems and it is represented by a parabolic equation, linear in the diffusion operator, and a reaction function f(u) = u(a-bu). They are referred to as semi linear equations. The a and b coefficients involve parameters and considerations of interest in neutronic flux. Thus it is reasonable to search for non trivial, positive and bounded solutions. (author)

[en] The document includes 6 papers on the measurement, calculation and evaluation of neutron reactions cross-sections. Refs, figs and tabs

[en] Based on a critical analysis of experimental data as well as nuclear reaction models calculations available, the most accurate theoretical frame for bach of the neutron induced reactions presented in part I is concluded. In the context of theoretical estimation of neutron cross-sections, several codes of prime importance are briefly discussed. (author)

[en] Abstract only

No abstract available

[en] CINDA, the Computer Index of Neutron Data, contains bibliographic references to measurements, calculations, reviews and evaluations of neutron cross-sections and other microscopic neutron data. The present issue, CINDA-A (1935-1987) vol. 5, is an index to all work on neutron nuclear data from the time of the discovery of the neutron until the end of 1987, for the elements 84 Polonium to 105 Hahnium. It is supplemented by the current issue, CINDA 90, which covers the references from 1988 to 1990

[en] A systematics is recommended to obtain the parameters for describing (n,2n) excitation functions by the constant temperature Weisskopf formula. (author)

[en] We have completed a new set of total cross section measurements, snd have measured approximately 36 additional samples. The goal of the new measurements was 1% statistical accuracy in 1% energy bins with systematic errors less than 1%. This was achieved for all but the smallest samples, for which the statistical accuracy was as large as 2% in 1% bins. However, the energy resolution is significantly better than this at low energies. The samples were: * The APT spallation target material: W * Medium-mass stmctural materials: Ti, V, Cr, Mn, Fe, Co, Ni * Actinides: Th, depleted U * Other materials for global optical model development: F, Mg, P, S, K, Y, Mo, In, Au, Hg, natural Pb * Separated isotopes of light nuclei: ⁶Li%, ⁷Li, ¹⁰B, ¹¹B, ¹³C, * Medium- and heavy-mass separated isotopes: ^54,56Fe, ^{182,183,184,186}W * Few-nucleon physics: H, D

[en] CINDA, the Computer Index of Neutron Data, contains bibliographical references to measurements, calculations, reviews and evaluations of neutron cross-sections and other microscopic neutron data. The present issue, CINDA-A (1935-1987) vol. 1, is an index to all work on neutron nuclear data from the time of the discovery of the neutron until the end of 1987, giving a listing for collective entries and compounds and a detailed explanation of CINDA

[en] Capture spectra for Au, Tm, Rh, and Ir were measured for neutrons of incident energy E=0.5, 0.7, 1, 2, and 3MeV