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The Global ETD Search service is a free service for researchers
to find electronic theses and dissertations. This service is
provided by the
Networked Digital Library of Theses and Dissertations.
Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
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Showing 81 to 90 of 2275 (0.042 seconds)Spelling suggestions: "subject:"neutron"" "subject:"deutron""
| 81 |
Anisotropic heat transfer inside rotating neutron starsHui, Chung-yue., 許宗宇. January 2004 (has links)
published_or_final_version / abstract / toc / Physics / Master / Master of Philosophy
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| 82 |
Flux map and reactivity measurements in the TRIGA Mark 1 reactorCarmack, Charles William, 1947- January 1971 (has links)
No description available.
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| 83 |
Time and space dependent neutron flux in an externally moderated spherical cavityForehand, Harry MacDonald, 1941- January 1973 (has links)
No description available.
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| 84 |
An epithermal neutron beam approach to boron neutron capture therapyNoonan, Denise Jane 05 1900 (has links)
No description available.
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| 85 |
Chemical binding effects on neutron slowing down and capture rates in the resonance regionSt. John, Holger Edgar 12 1900 (has links)
No description available.
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| 86 |
Application of variational synthesis to solutions of multidimensional neutron transport problemsCobb, William Ronald 12 1900 (has links)
No description available.
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| 87 |
Very intense continuous high flux pulsed reactorNarain, Rajendra 12 1900 (has links)
No description available.
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| 88 |
Nuclear activation techniques and methods of elemental concentration determination in bioenvironmental studiesFarooqi, Asad Saeed January 1991 (has links)
No description available.
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| 89 |
The Lattice Boltzmann Method applied to linear particle transport / Bernard ErasmusErasmus, Bernard January 2012 (has links)
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigated.
The transport model used, is derived from the Boltzmann equation for neutral particles by inverting
the streaming operator and casting the integral transport equation into an operator form. From the
operator equation, an iterative solution to the transport problem is presented, with the first collision
source as the starting point for the iteration scheme. One of the main features of the method is the
simultaneous discretization of the phase space of the problem, whereby particles are restricted to
move on a lattice.
A full description of the discretization scheme is given along with the iterative procedure and
quadrature set used for the angular discretization. To mitigate lattice ray effects, an angular
refinement scheme is introduced to increase the angular coverage of the problem phase space.
The method is then applied to a model problem to investigate its applicability to neutron transport.
Three cases are considered where constant, linear and exponential interpolants are used to account
for the accumulation of flux due to the streaming of particles between nodes. The results obtained
are compared to a reference solution, that was calculated by using the MCNP code and to the values
calculated using a nodal SN method. Finally, areas of improvement are identified and possible
extensions to the algorithm are provided. / Thesis (MIng (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013
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| 90 |
The Lattice Boltzmann Method applied to linear particle transport / Bernard ErasmusErasmus, Bernard January 2012 (has links)
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigated.
The transport model used, is derived from the Boltzmann equation for neutral particles by inverting
the streaming operator and casting the integral transport equation into an operator form. From the
operator equation, an iterative solution to the transport problem is presented, with the first collision
source as the starting point for the iteration scheme. One of the main features of the method is the
simultaneous discretization of the phase space of the problem, whereby particles are restricted to
move on a lattice.
A full description of the discretization scheme is given along with the iterative procedure and
quadrature set used for the angular discretization. To mitigate lattice ray effects, an angular
refinement scheme is introduced to increase the angular coverage of the problem phase space.
The method is then applied to a model problem to investigate its applicability to neutron transport.
Three cases are considered where constant, linear and exponential interpolants are used to account
for the accumulation of flux due to the streaming of particles between nodes. The results obtained
are compared to a reference solution, that was calculated by using the MCNP code and to the values
calculated using a nodal SN method. Finally, areas of improvement are identified and possible
extensions to the algorithm are provided. / Thesis (MIng (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013
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