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Showing 1 to 11 of 11 for “"Neutron cross section"”.
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Calculations of neutron damage cross-sections in silicon, gallium arsenide and iron
The neutron cross-section processing code NJOY has been modified to calculate total displacements kerma cross-sections for silicon, gallium, arsenic and gallium arsenide. The modified NJOY is also used to calculate the displacement cross-sections for iron.
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Measurement of the electric form factor of the neutron at low momentum transfers using a vector polarized deuterium gas target at BLAST
… form factors are well known, knowledge of the neutron form factors has been limited due to the lack of pure neutron targets. Few nucleon targets, deuterium in particular, are typically used to study the electromagnetic structure of the neutron. Cross section measurements are not sufficient for …
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Tightly coupled neutronics and thermal-hydraulics using open-source software
Coupling the neutronic and thermal-hydraulic analyses of a nuclear reactor core is important because it helps identify the most relevant safety issues. Currently all coupled computations solve the same set of governing equations using different coupling methods, which can be sorted into two …
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Medical Isotope Production of Actinium 225 By Linear Accelerator Photon Irradiation of Radium 226
… of Radium-226 (half-life 1600yrs). The photo-neutron reaction liberates neutrons from Ra-226 atoms leaving behind Radium-225 (half-life 14.7 days). Ra-225 decays naturally through beta emission to Ac-225. Previous research demonstrated it is possible to produce Ac-225 using a LINAC; however, …
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Experimental approaches for the production of thorium-229
… Ridge National Laboratory (ORNL) and 2) the fast neutron irradiation of a 230Th target in a particle accelerator. This thesis outlines several experiments completed at ORNL to test the feasibility and preparation procedures for these two production methods. First, we experimentally evaluated the …
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Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico
… compiled for this work. The EVENT (EVEn parity Neutron Transport) radiation transport code was chosen to analyze and verify the steady-state and time-dependent experimental configurations on the AGN. Complex AGN models were developed to test the EVENT code and the case-dependent multigroup …
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Enhanced corrosion of zirconium-based alloys in proximity to other metals : the "shadow effect"
… must be corrosion resistant, have low thermal neutron cross section, and high strength. Corrosion resistance is one of the most important parameters for reactor materials. From the beginning of the use of reactors, engineers have been faced with the problem of excessive corrosion in several …
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A new unresolved resonance region methodology
… sequences, the temperature-dependent cross sections are calculated on a small grid around the energy of reference using the RML formalism and the Leal-Hwang Doppler broadening methodology. The effective cross sections calculated at the energy of reference are then used to construct …
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GPU-Oriented Algorithms for Continuous Energy Monte Carlo Neutron Transport
… take place in continuous energy Monte Carlo (MC) neutron transport simulations. These simulations play a crucial role in designing fission, fusion, and security systems that may play a pivotal role in the transition to a decarbonized world. This work contributes to adapting continuous energy MC …
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Messung von Wirkungsquerschnitten für die Streuung von Neutronen im Energiebereich von 2 MeV bis 4 MeV mit der 15N(p,n)-Reaktion als Neutronenquelle
… benötigt. Insbesondere der Neutronentransport in einem Blei-Spallationstarget eines beschleunigergetriebenen unterkritischen Reaktors hängt stark von den inelastischen Streuquerschnitten im Energiebereich von 0,5 MeV bis 6 MeV ab. In den vergangenen 20 Jahren wurden …