Thermal Neutron Spectrum Measurements By Foil Activation
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Thermal Neutron Spectrum Measurements By Foil Activation
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Author : Stanford University. Department of Mechanical Engineering. Nuclear Engineering Division
language : en
Publisher:
Release Date : 1967
Thermal Neutron Spectrum Measurements By Foil Activation written by Stanford University. Department of Mechanical Engineering. Nuclear Engineering Division and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1967 with categories.
Thermal Neutron Spectrum Measurement By Foil Activation
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Author : Higino Herrera Ibarra
language : en
Publisher:
Release Date : 1966
Thermal Neutron Spectrum Measurement By Foil Activation written by Higino Herrera Ibarra and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1966 with Neutrons categories.
The Measurement Of Thermal Neutron Spectra In Heterogeneous Lattices By Foil Activation
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Author : Gregg Woodford Dixon
language : en
Publisher:
Release Date : 1970
The Measurement Of Thermal Neutron Spectra In Heterogeneous Lattices By Foil Activation written by Gregg Woodford Dixon and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1970 with Lattices categories.
Proceedings Of The Brookhaven Conference On Neutron Thermalization Experimental Aspects Of Transient And Asymptotic Phenomena
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Author : Brookhaven National Laboratory
language : en
Publisher:
Release Date : 1962
Proceedings Of The Brookhaven Conference On Neutron Thermalization Experimental Aspects Of Transient And Asymptotic Phenomena written by Brookhaven National Laboratory and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with Neutrons categories.
Foils
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Author : W. C. Morgan
language : en
Publisher:
Release Date : 1964
Foils written by W. C. Morgan and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1964 with Graphite categories.
Neutron Spectrum Determinations At Low Flux Levels
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Author : Paul Kruger
language : en
Publisher:
Release Date : 1960
Neutron Spectrum Determinations At Low Flux Levels written by Paul Kruger and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Gamma rays categories.
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.
Measurement Of Neutron Spectrum Age And Diffusion Length In Concrete
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Author : Gene M. Lim
language : en
Publisher:
Release Date : 1967
Measurement Of Neutron Spectrum Age And Diffusion Length In Concrete written by Gene M. Lim and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1967 with categories.
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).
Measurement Of Neutron Flux And Spectra For Physical And Biological Applications
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Author : National Committee on Radiation Protection and Measurements (U.S.)
language : en
Publisher:
Release Date : 1960
Measurement Of Neutron Flux And Spectra For Physical And Biological Applications written by National Committee on Radiation Protection and Measurements (U.S.) and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Neutron flux categories.
Measurement Of Neutron Flux Spectra In A Tungsten Benchmark By Neutron Foil Activation Method
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Author : Cezar Ciprian Negoita
language : en
Publisher:
Release Date : 2004
Measurement Of Neutron Flux Spectra In A Tungsten Benchmark By Neutron Foil Activation Method written by Cezar Ciprian Negoita and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2004 with categories.
Neutron Spectral Measurements And Calculation Comparisons Of Idaho State University Agn 201 Reactor
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Author :
language : en
Publisher:
Release Date : 2013
Neutron Spectral Measurements And Calculation Comparisons Of Idaho State University Agn 201 Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013 with categories.
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.