Download or read book Comparison of Calculated and Experimental Neutron Spectra from the LLL Pulsed Sphere Program Using the TART Monte Carlo Code and the LLL Evaluated Nuclear Data Library written by and published by . This book was released on 1972 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-08 with total page 958 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1975 with total page 972 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science and Engineering written by and published by . This book was released on 1978 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Annual Index written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1986 with total page 532 pages. Available in PDF, EPUB and Kindle. Book excerpt: Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1975 with total page 652 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transactions of the American Nuclear Society written by and published by . This book was released on 1974 with total page 1062 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Index written by and published by . This book was released on 1975 with total page 1076 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements written by and published by . This book was released on 1975-10-17 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Summary of Measurements and Calculations of Neutron and Gamma ray Emission Spectra from Spheres Pulsed with 14 MeV Neutrons written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A tabulation of the spherical assemblies for which the transport of 14-MeV neutrons have been measured using pulsed sphere and time-of-flight techniques is presented. The description of the measurements and their comparison with the predictions of LLNL Monte Carlo calculations using the ENDL and ENDF (III to V versions) libraries can be found in the publications listed in the references.
Download or read book Comparison of Discrete ordinates and Monte Carlo Calculations with Measurements of Fast Neutron Spectra in Paraffin Shields written by A. E. Profio and published by . This book was released on 1967 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt: Measurements of the fast neutron angular flux spectrum in CH2 have been made in point-source, cylindrical geometry, using the same time-of-flight method previously applied to spherical and infinite medium geometries. This work is a continuation of the comparison of accurate, detailed, high-resolution measurements with DTF-IV discrete-ordinate and O5R Monte Carlo calculations. The sphere experiment was reanalyzed with a P16 Gauss-Legendre quadrature set in DTF-IV using the best available evaluated cross sections and P3 scattering. Reasonably good agreement was found except near 0 deg. where the discrete-ordinate code fails to calculate the very anisotropic flux. 05R calculations were made with a more complete description of the spectrum and angular distribution of the source neutrons, and included the continuum inelastic scattering, using new source generator and general inelastic scattering subroutines written for this research. Differences were small. An angular flux cylinder analysis program was written for 05R and unbiased calculations were made for the cylinder. Variance-reduction schemes are needed, however, for a meaningful comparison with the cylinder measurements. The DTF-IV code (1DF version) was put into operation on the Kirtland CDC6600 computer and the report includes input instructions. (Author).
Download or read book Comparison of Measured Neutron and Proton Spectra with Calculated Spectra in the Energy written by and published by . This book was released on 1964 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Monte Carlo Procedure for Calculating Penetration of Neutrons Through Straight Cylindrical Ducts written by D. G. Collins and published by . This book was released on 1961 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Monte Carlo m thod is applied to evaluate the energy and angular distributions and the intensity of the scattered neutron flux that penetrates a straight cylindrical duct. A discussion of the scattering theory involved is given, as well as the sampling techniques peculiar to the duct-penetration problem. The method is evaluated on the basis of comparisons with experimental data. (Author).
Download or read book Time Dependent Monte Carlo Calculations of the ORELA Oak Ridge Electron Linear Accelerator Target Neutron Spectrum written by and published by . This book was released on 1990 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: The time dependent spectrum of neutrons in the water-moderated Oak Ridge Electron Linear Accelerator (ORELA) target has been calculated using a modified version of the MORSE multi-group Monte Carlo code with an analytic hydrogen scattering model. Distributions of effective neutron distance traversed in the target are estimated with a time and energy dependent algorithm from the leakage normal to the target face. These data are used in the resonance shaped analyses of time-of-flight cross section measurements to account for the experimental resolution function. The 20 MeV--10 eV energy range is adequately represented in the MORSE code by the 174 group VITAMIN-E cross section library with a P5 expansion. An approximate representation of the ORELA positron source facility, recently installed near the target, has been included in the calculations to determine any perturbations the positron source might create in the computed neutron distributions from the target. A series of coupled Monte Carlo calculations was performed from the target to the positron source and back to the target using a next-event estimation surface source for each step. The principal effect of the positron source was found to be an increase in the distance for the lower energy neutron spectra, producing no real change in the distributions where the ORELA source is utilized for experiments. Different configurations for the target were investigated in order to simulate the placement of a shadow bar in the neutron beam. These beam configurations included neutrons escaping from : (1) the central tantalum plates only, (2) the entire target with the tantalum plates blocked out, and (3) only a small area from the water. Comparisons of the current data with previous calculations having a less detailed model of the tantalum plates have been satisfactory. 10 refs.
Download or read book TARTNP written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A Monte Carlo code was written that calculates the transport of neutrons, photons, and neutron-induced photons. The cross sections of these particles are derived from TARTNP's data base, the Evaluated Nuclear Data Library. The energy range of the neutron data in the Library is 10−9 MeV to 20 MeV; the photon energy range is 1 keV to 20 MeV. One of the chief advantages of the code is its flexibility: it allows up to 17 different kinds of output to be evaluated in the same problem.
Download or read book Development and Implementation of Photonuclear Cross Section Data for Mutually Coupled Neutron Photon Transport Calculations in the Monte Carlo N Particle MCNP Radiation Transport Code written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The fundamental motivation for the research presented in this dissertation was the need to development a more accurate prediction method for characterization of mixed radiation fields around medical electron accelerators (MEAs). Specifically, a model is developed for simulation of neutron and other particle production from photonuclear reactions and incorporated in the Monte Carlo N-Particle (MCNP) radiation transport code. This extension of the capability within the MCNP code provides for the more accurate assessment of the mixed radiation fields. The Nuclear Theory and Applications group of the Los Alamos National Laboratory has recently provided first-of-a-kind evaluated photonuclear data for a select group of isotopes. These data provide the reaction probabilities as functions of incident photon energy with angular and energy distribution information for all reaction products. The availability of these data is the cornerstone of the new methodology for state-of-the-art mutually coupled photon-neutron transport simulations. The dissertation includes details of the model development and implementation necessary to use the new photonuclear data within MCNP simulations. A new data format has been developed to include tabular photonuclear data. Data are processed from the Evaluated Nuclear Data Format (ENDF) to the new class ''u'' A Compact ENDF (ACE) format using a standalone processing code. MCNP modifications have been completed to enable Monte Carlo sampling of photonuclear reactions. Note that both neutron and gamma production are included in the present model. The new capability has been subjected to extensive verification and validation (V & V) testing. Verification testing has established the expected basic functionality. Two validation projects were undertaken. First, comparisons were made to benchmark data from literature. These calculations demonstrate the accuracy of the new data and transport routines to better than 25 percent. Second, the ability to calculate radiation dose due to the neutron environment around a MEA is shown. An uncertainty of a factor of three in the MEA calculations is shown to be due to uncertainties in the geometry modeling. It is believed that the methodology is sound and that good agreement between simulation and experiment has been demonstrated.
