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Showing 1 to 20 of 94 for “"Neutron flux"”.
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Neutron flux perturbation by foil detectors
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Physics, 1961.
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The Determination of the Thermal Neutron Flux in a Research Reactor
Since a research reactor serves as a neutron source for a large number of experiments, knowledge of the neutron flux, and of its spatial and spectral energy distribution is of great importance, not only for purposes of experimental reactor physics (e.g., determination of specific data with regard …
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Neutron flux characterization of the Kansas State University TRIGA Mark II’s Northeast Beam Port
A high-resolution, multi-dimensional flux characterization was performed for the Kansas State University TRIGA Mark II’s Northeast Beam Port for the purpose of informing future experimental work, such as detector characterization, done using the beam. First, the Beam Port geometry was added to the …
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Measurement of neutron flux spectra in a Tungsten Benchmark by neutron foil activation method
… concept, rely on the results of neutron physical calculations. These depend on the knowledge of the neutron and photon flux spectra which is particularly important because it permits to anticipate the possible answers of the whole structure to phenomena such as nuclear heating, …
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Spatial distribution of the neutron flux on the surfaces of a graphite-lined cavity
Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962.
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Measurement of neutron flux and spectrum-averaged cross sections for an in-pile PWR loop
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.
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Design and construction of an automatic neutron flux scanner for the MIT heavy water lattice facility
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962.
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Effects of neutron flux gradient and detector-vibrator geometry on the local-global responses of the UTR-10 reactor
<p>http://www.worldcat.org/oclc/8741798</p>
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A semi-experimental nodal synthesis method for the on-line reconstruction of three-dimensional neutron flux-shapes and reactivity
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1991.
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Neutron exposure and neutron flux in Asymptotic Giant Branch stars: a study of neutron capture cross sections of Zr isotopes
… This work concerns the measurements of the neutron capture cross sections of 90,91,92,93,94,96Zr isotopes, performed at the time-of-flight facilities n_TOF at CERN and GELINA at IRMM and their implication in stellar modeling.
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Determining the moderator temperature coefficient in a PWR by stochastic fluctuation analysis
… model. The method correlates fluctuations in the neutron flux with fluctuations in the coolant temperature. Results show that the frequency response function between the in-core neutron flux and thermocouple signals is proportional to the MTC and can be used to monitor changes in the MTC …
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Benchmarking photoneutron production of Mcnpx simulations with experimental results
… reactor is the generation of a high-energy neutron flux. The neutron flux can be generated by hitting a high-Z target composed of lead, tungsten, or other elements with a high-energy proton beam; To explore the control issues arising from coupling a proton accelerator to a subcritical …
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Neutronics analysis for cylindrical assembly using Green's functions
… reactor properties. These properties include the neutron flux, criticality condition, or distribution of material in the assembly. It is possible to obtain an analytic solution for the neutron flux for a reactor represented in cylindrical coordinates using a Green's function or Green's function …
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A Monte Carlo analysis of neutron thermalization in graphite
… Polytechnic Institute is to be used as a pulsed neutron source. The time dependence of neutron flux, energy spectrum as a function of time, and various reactor parameters such as Fermi Age, slowing dotm time, and diffusion length in graphite will be measured using the pulsed source method. This …
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An application of Chebyshev polynomials to the solution of a two-dimensional elliptic boundary-value problem
… to approximate solutions to the two-dimensional neutron diffusion equation. The two-dimensional two-group neutron diffusion equations are solved by expanding neutron fluxes in a finite series of Chebyshev polynomials over large regions of a fission reactor. All the equations for the expansion …
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Characterizing the influence of neutron fields in causing single-event effects using portable detectors
… Effects(SEEs). In the atmosphere, secondary neutrons are the dominant particles causing this effect. The neutron flux density in atmosphere is very low. For a good statistical certainty, millions of device hours are required to measure the event rate of a device in the natural environment. …
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Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients
To model the neutronic physics behavior of the core in CANDU pressure tube type heavy water reactors with natural-uranium fuel, two levels of calculations are required. Initially, lattice-level transport calculations are carried out to obtain, with high detail and accuracy, the flux distribution …
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Feasibility study of compact Neutron Resonance Transmission Analysis using a linac, a fusion-based neutron generator, and an isotopic source
… nuclear materials in a black box target. Neutron Resonance Transmission Analysis (NRTA) is a spectroscopic technique which uses resonant neutron absorption to identify isotopic compositions. Previous NRTA experiments have used expensive beam line facilities with kilometer-long …
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