Author: Higino Herrera IbarraPublisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 113
Book Description
Thermal Neutron Spectrum Measurement by Foil Activation
Author: Higino Herrera IbarraPublisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 113
Book Description
Thermal Neutron Spectrum Measurements by Foil Activation
Author: Stanford University. Department of Mechanical Engineering. Nuclear Engineering DivisionPublisher:
ISBN:
Category :
Languages : en
Pages : 92
Book Description
The Measurement of Thermal Neutron Spectra in Heterogeneous Lattices by Foil Activation
Author: Gregg Woodford DixonPublisher:
ISBN:
Category : Lattices
Languages : en
Pages : 158
Book Description
FOILS
Author: W. C. MorganPublisher:
ISBN:
Category : Graphite
Languages : en
Pages : 28
Book Description
Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author: National Committee on Radiation Protection and Measurements (U.S.)Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 104
Book Description
Measurement of Neutron Flux Spectra in a Tungsten Benchmark by Neutron Foil Activation Method
Author: Cezar Ciprian NegoitaAdvanced Technologies and Applications of Neutron Activation Analysis
Author: Lylia Alghem HamidatouPublisher:
ISBN: 1789859735
Category : Chemistry
Languages : en
Pages : 123
Book Description
This book highlights the advanced technologies and applications of neutron activation analysis (NAA). It discusses the latest developments influencing the performance and utility of different NAA techniques across wide areas of applications: nuclear technology, industry, medicine, clinical investigations, biology, geochemistry, soil contamination, waste management, diet, lifestyle and health, cosmology, archeology, forensic science, etc. The overall goal of the book is to promote innovation and development of NAA techniques, technologies, and nuclear culture by presenting high-quality chapters with numerous results at both national and international levels. The book will serve as a source for graduate and postgraduate students in nuclear sciences and applications and nuclear analytical techniques, experienced practitioners who want to implement or use other varieties of NAA, professional technicians and analysts, users of NAA, and other stakeholders who wish to better understand NAA techniques.
Proceedings of the Brookhaven Conference on Neutron Thermalization: Experimental aspects of transient and asymptotic phenomena
Author: Brookhaven National LaboratoryPublisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 356
Book Description
Thermal and Fission Neutron Flux Measurements in Process Tubing and in Neutron Activation Test Locations
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 13
Book Description
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.
Measurement of Neutron Spectrum, Age, and Diffusion Length in Concrete
Author: Gene M. LimPublisher:
ISBN:
Category :
Languages : en
Pages : 30
Book Description
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).