Some notes on the calculation of energy-angle correlated distributions with TNG and their representation in File 6 formats

The model code TNG has been extensively used in evaluation work of structural materials for ENDF/B-VI performed at Oak Ridge National Laboratory. A new aspect of ENDF/B-VI is the use of File 6 formats for energy-angle correlated data. Such data are generally calculated, anchored by experimental data. In this informal note we outline how the TNG results are calculated and entered in the File 6 formats. 4 refs

Neutron emission spectra induced by 14-MeV neutrons from the Evaluated Nuclear Data File (ENDF/B-V): a critical review

Neutron emission spectra induced by 14.6-MeV incident neutrons, retrieved from ENDF/B-V, are graphically compared with experimental data by Hermsdorf et al. and Clayeux and Voignier. The elements selected for the comparisons include Na, Mg, Al, Si, Ca, Ti, V, Cr, Fe, Ni, Cu, Nb, W, and Pb. In addition to comparing the evaluated total neutron emission spectra with experimental data, individually evaluated spectra from contributing reactions are presented. Only a few of the evaluated spectra were found to agree well with the measured spectra, namely, those evaluations which utilized advanced nuclear model codes with precompound effects and competing binary and tertiary reactions. Recommendations for removing several defects in most evaluations are made. 3 figures

RIVER-RAD: A computer code for simulating the transport of radionuclides in rivers

A screening-level model, RIVER-RAD, has been developed to assess the potential fate of radionuclides released to rivers. The model is simplified in nature and is intended to provide guidance in determining the potential importance of the surface water pathway, relevant transport mechanisms, and key radionuclides in estimating radiological dose to man. The purpose of this report is to provide a description of the model and a user's manual for the FORTRAN computer code

Infrared Features of the Landau Gauge QCD

The infrared features of Landau gauge QCD are studied by the lattice simulation of $\beta=6.0, 16^4, 24^4, 32^4$ and $\beta=6.4, 32^4, 48^4$. We adopt two definitions of the gauge field; 1) $U-$linear 2) $\log U$ and measured the gluon propagator and ghost propagator. Infrared singularity of the gluon propagator is less than that of tree level result but the gluon propagator at 0 momentum remains finite. The infrared singularity of ghost propagator is stronger than the tree level. The QCD running coupling measured by using the gluon propagator and the ghost propagator has a maximum $\alpha_s(p)\simeq 1$ at around $p=0.5GeV$ and decreases as $p$ approaches 0. The data are analyzed in use of formula of the principle of minimal sensitivity(PMS), the effective charge method and the contour-improved perturbation method, which suggest necessity of the resummation of perturbation series in the infrared region together with existence of the infrared fixed point. Kugo-Ojima parameter saturates at about -0.8 in contrast to the theoretically expected value -1.Comment: RevTex4, 9 pages, 10 eps figures, Typos corrected. To be published in Phys. Rev. D(2004

Evaluation and testing of double differential Fe(n,n') cross sections

Analyses of integral experiments that include thick (>15 cm) iron regions have shown a consistent underprediction of neutron transmission. One explanation that has been offered is that the angular distributions of the inelastically scattered neutrons in the continuum in the current ENDF/B-V iron evaluation were assumed to be isotropic. In reality, these distributions are forward peaked, especially if the incident neutron energies (E/sub n/) are a few MeV greater than the continuum Q-value. The forward peaking also increases with increasing outgoing neutron energies (E/sub n/'), giving rise to correlated energy-angle distributions. In order to understand their effects on neutron penetration through iron, we generated such correlated distributions in a special update of the ENDF/B-V Mod-3 iron evaluation and re-analyzed an iron sphere problem. 9 refs., 2 figs

Experience in using the covariances of some ENDF/B-V dosimetry cross sections: proposed improvements and addition of cross-reaction covariances

Recent ratio data, with carefully evaluated covariances, were combined with eleven of the ENDF/B-V dosimetry cross sections using the generalized least-squares method. The purpose was to improve these evaluated cross sections and covariances, as well as to generate values for the cross-reaction covariances. The results represent improved cross sections as well as realistic and usable covariances. The latter are necessary for meaningful intergral-differential comparisons and for spectrum unfolding

Calculated neutron-induced cross sections for /sup 63,65/Cu /sup 58,60/Ni, and /sup 52/Cr from 1 to 20 MeV and comparisons with experiments

Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 63,65/Cu, /sup 58,60/Ni, and /sup 52/Cr for incident energies from 1 to 20 MeV. The input parameters for the model codes determined through analysis of experimental data in this energy region. The models used, the input data, the resulting calculations, and comparisons with measured data are discussed. 15 refs

Description of evaluation for /sup 50,52,53,54/Cr performed for ENDF/B-VI

Isotopic evaluations for /sup 50,52,53,54/Cr performed for ENDF/B-VI are briefly reviewed. The evaluations are based on analysis of experimental data and results of model calculations which reproduce the experimental data. Evaluated data are given for neutron induced reaction cross sections, angular and energy distributions, and for gamma-ray production cross sections associated with the reactions. File 6 formats are used to represent energy-angle correlated data and recoil spectra. Uncertainty files are included for the major cross sections. Detailed evaluations are given for /sup 52,53/Cr, and results of calculations for reactions with large cross sections are used for evaluation of the minor isotopes. 27 refs., 6 figs

Description of evaluations for /sup 58,60,61,62,64/Ni performed for ENDF/B-VI

Isotopic evaluations for /sup 58,50,61,62,64/Ni performed for ENDF/B-VI are briefly reviewed. The evaluations are based on analysis of experimental data and results of model calculations which reproduce the experimental data. Evaluated data are given for neutron induced reaction cross sections, angular and energy distributions, and for gamma-ray production cross sections associated with the reactions. File 6 formats are used to represent energy-angle correlated data and recoil spectra. Uncertainty files are included for the major cross sections. Detailed evaluations are given for /sup 58/60/Ni, and results of calculations for the major reactions are used for evaluations of the minor isotopes. 29 refs., 8 figs

Description of evaluation for /sup 63,65/Cu for ENDF/B-VI

Isotopic evaluations for /sup 63,65/Cu performed for ENDF/B-VI are briefly reviewed. The evaluations are based on analysis of experimental data and results of model calculations which reproduce the experimental data. Evaluated data are given for neutron-induced reaction cross sections, angular and energy distributions, and for gamma-ray production cross sections associated with the reactions. File 6 formats are used to represent energy-angle correlated data and recoil spectra. Uncertainty files are included for the major cross sections. Full evaluations are given for /sup 63,65/Cu