[en] The aim of this is to derive a reliable neutron spectrum information to be used in further shielding calculation. Consequently, it was intended to improve the quality of these information by emphasizing correct evaluation of the related uncertainty data. In order to meet these objectives, existing methods and procedures for neutron spectrum calculation and measurement were improved. (author)

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[en] The calculated sensitivity coefficients show that in a hybrid reactor the greatest influence on the principal functionals is exerted by the secondary neutron spectra of the reactions /sup 238/U(n, 2n), /sup 23B/U(n, n/prime/) cont, and Fe(n, n/prime/) cont, for which the contribution to the fission rate in /sup 238/U and, therefore, in neutron multiplication per source neutron, may be considerable. The indeterminacy of the functionals, owing to the 15-20% inaccuracy of the spectra, is estimated for the hybrid reactor model studied to be 3-4.5% for the fission rate and 2-2.5% for the tritium yield

[en] The program ANS which is the graphical user friendly program to process evaluated neutron data files for interpretation of transmission experiments. The ANS program was written in the Turbo Pascal v. 5 language and may work on the IBM AT with Math CoProcessor. 3 refs.; 1 fig

[en] Results from the HP irradiation test have been shown to reduce uncertainties associated with calculation of axial and radial flux and reaction rate distributions, flux perturbations due to core heterogeneities, neutron flux and reaction rates outside the fuel region, activation of structural components and sodium, and fuel burnup. Improved knowledge of reaction rates (hence burnup, power and flux distributions) is expected to result in better prediction of the performance of experiments irradiated in FFTF

[en] The measurement of the neutron spectrum from the White Sands Missile Range Fast Burst Reactor (FBR) in the presence of the experimenter's table is reported. A reinvestigation of this neutron spectrum was performed as a result of a recently published work, which indicates that the experimenter's table has a considerable softening effect on the neutron spectrum from the FBRF. Based on such spectral parameeters as average energy, integral fluence, and spectral index, we find the neutron spectrum associated with the experimenter's table to be essentially identical to the free-field leakage spectrum

[en] The consequences of the evaporation of prompt neutrons and γ-rays from primary fission fragments in the spontaneous fission of 252Cf have been examined by a Nonte-Carlo method. A semiempirical mass equation and experimental values of total kinetic energies are used to obtain the sum of excitation energies of complementary fragments. The division of this energy between complementary fragments is determined by the two-spheroid model for the scission configuration. The prompt neutron multiplicity distribution is found to be Gaussian about an average value of 3.684. Calculated values of the average number of prompt neutrons and the average values of the total γ-rays energies of complementary fragments as a function of fragments mass are in good agreement with the experimental values. Calculated results for the charge dependence of total γ-ray energies show an odd-even effect, whereas no such effect is apparent in the charge dependence of the average number of neutron. Mass and charge distributions of secondary fission fragments are also well reproduced in the calculations

[en] The fast neutron spectrum of the Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is being used to study and standardize fast reactor neutron dosimetry materials and methods. The CFRMF has been designated a ''benchmark experiment'' to test the cross section data of dosimetry materials as well as other materials used and produced in fast reactors. Information about the neutron energy spectrum of the CFRMF is presented

No abstract available