Download or read book Thermal Neutron Spectrum Measurements by Foil Activation written by Stanford University. Department of Mechanical Engineering. Nuclear Engineering Division and published by . This book was released on 1967 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal Neutron Spectrum Measurement by Foil Activation written by Higino Herrera Ibarra and published by . This book was released on 1966 with total page 113 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Measurement of Thermal Neutron Spectra in Heterogeneous Lattices by Foil Activation written by Gregg Woodford Dixon and published by . This book was released on 1970 with total page 158 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Neutron Flux and Spectra for Physical and Biological Applications written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1960 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the Brookhaven Conference on Neutron Thermalization Experimental aspects of transient and asymptotic phenomena written by Brookhaven National Laboratory and published by . This book was released on 1962 with total page 356 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Spectral Measurements and Calculation Comparisons of Idaho State University AGN 201 Reactor written by and published by . This book was released on 2013 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this experiment was to determine the neutron spectrum of the ISU AGN201 reactor using both computer calculations and physical measurements and then to make comparisons between the results provided by the different methods. The regions of interest in the reactor for neutron spectral measurements were the core center region and the reflector region. Computer simulations performed using MCNP5 and DISNEL were both used to obtain neutron spectra. For the experimental portions, several foils were irradiated in the regions of interest. Each foil had a unique response function and could thus provide independent information that could then be used to obtain a neutron spectrum. Since there were fewer foil activation responses than the desired number of energy groups, the problem was under-determined; therefore, unfolding methods had to be utilized. The modified least-squares method and the maximum entropy method were both used. The MAXED software package was used for the maximum entropy method. MAXED indicated spectra with higher thermal neutron contributions and lower fast neutron contributions than the default MCNP spectra indicated for both the center and reflector regions. The modified least-squares method was very consistent with default MCNP spectra and provided significant uncertainty reduction. DISNEL and MCNP agreed very well for the center spectrum and fairly well for the reflector spectrum. This consistency illustrates that MCNP, with the most current set of cross-sections, and spectral measurement methods using the analysis tools described herein, are equally reliable methods of determining neutron spectra in a reactor of the relative simplicity of the AGN reactor.
Download or read book Measurement of Neutron Flux and Spectra for Physical and Biological Applications written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1960 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurements of the Distribution of Thermal Neutrons and Rh resonance Neutrons in Isotope Channel 5 11 by Means of Foil Activation written by Kjell Steenberg and published by . This book was released on 1951 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal and Fission Neutron Flux Measurements in Process Tubing and in Neutron Activation Test Locations written by and published by . This book was released on 1961 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron activation analysis provides the extremely high sensitivity necessary for the measurement of many trace elements. Activation techniques are presently being used to measure the concentrations of various undesirable parent isotopes in reactor process tubing, slug jackets and their corrosion film, and in process vater and vater treatment chemicals. The interpretation of results from activation analysis are sometimes complicated by the fact that a given radioisotope may be produced by fission neutrons (threshold reactions) from other elements as well as by the more common thermal neutron (n, [gamma]) reactions. Shielding the sample with cadmium prior to irradiation or irradiating in the graphite reflector will minimize the contributions from thermal or fission neutrons, respectively. The purpose of this study has been to measure the ratios and magnitudes of the thermal and fission fluxes in process tubing and to compare these with values at locations where neutron activations can be performed. Also, it was of interest to measure the ratios and magnitudes of the thermal and fission fluxes from a point in the lattice to a point well into the graphite reflector, and to determine if the fission neutron spectrum as measured by two threshold reactions, changes appreciably over this region. These data will aid in selecting the most favorable available positions for activations with thermal neutron reactions or with threshold reactions.
Download or read book Neutron Spectrum Determinations at Low Flux Levels written by Paul Kruger and published by . This book was released on 1960 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron flux measurements have been made (1)2 of low-level neutron sources present in several types of neutron-producing facilities. The flux levels or distribution of thermal, epithermal, and fast neutrons have been measured in radioisotope sources, spent fuel element gamma irradiation facilities, and electron linear accelerators. Sensitivities greater than 1 neutron per sq cm per sec have been achieved for thermal neutrons. Neutron flux measurements may be made by several methods (2). Foil activation (3) is a convenient and simple technique. The foils containing materials of known cross-section are exposed to the neutrons, and the flux determinations are made by measurement of the induced activities in the irradiated foils. This technique is widely used for measuring neutron fluxes and spectra in nuclear reactors and critical facilities where the neutron fluxes are large (106 to 1014 neutrons per sq cm per sec). To measure neutron fluxes of smaller magnitude, such as those found in isotope sources, gamma irradiation facilities, or outside reactor shielding (1⁄4106 neutrons per sq cm per sec), special foil dosimetry techniques or counting methods are required to obtain sufficient sensitivity for the radioactivity measurements. The theoretical and experimental considerations for neutron detectors of high sensitivity and several programs in which these detectors were used are discussed.
Download or read book Neutron Fluence Measurements written by International Atomic Energy Agency and published by . This book was released on 1970 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Neutron Spectrum Age and Diffusion Length in Concrete written by Gene M. Lim and published by . This book was released on 1967 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: Activation foil detectors were used to measure the fast-neutron spectrum, slowing-down age, and thermal-diffusion length in concrete. The neutron source was a uranium fission plate placed in the graphite thermal column of the University of Virginia Reactor. Experimental concrete slabs were placed in the concrete biological shield of the reactor so that the medium was essentially infinite in the lateral direction. Indium, magnesium, and aluminum threshold foils were used to map the fast flux; indium, gold, tungsten, and manganese resonance foils to measure the neutron age; and indium and gold foils to measure the thermal neutron distribution. The fast spectrum retains essentially the fission shape with a slight dip in the 3- to 5-MeV range. The measured ages are essentially the same, l49 cm to the indium, gold, and tungsten resonances and 126 sq cm to the manganese resonances. The thermal diffusion length was measured as 6.0 plus or minus 0.5 cm. (Author).
Download or read book Proceedings of the Brookhaven Conference on Neutron Thermalization April 30 May 2 1962 Neutron spectra in lattices and infinite media written by Brookhaven National Laboratory and published by . This book was released on 1962 with total page 598 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A THERMAL NEUTRON SPECTRUM MEASURED BY A CRYSTAL SPECTROMETER written by and published by . This book was released on 1963 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Neutron Flux Spectra in a Tungsten Benchmark by Neutron Foil Activation Method written by Cezar Ciprian Negoita and published by . This book was released on 2004 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Energy Spectrum of Leakage Neutrons from a Homogeneous Reactor written by R. C. Rohr and published by . This book was released on 1951 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
