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 Nuclear engineering (6)
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 Neutron transport theory (2)
 Neutrons  Diffraction<br />Nuclear reactors  Cores<br />Nuclear reactors  Missouri  Rolla (1)
 Ironaluminum alloys  Effect of radiation on<br />Orderdisorder in alloys<br />Radiation  Simulation methods (1)
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 Barium titanate (1)
 Decomposition (Chemistry)<br />Gamma rays<br />Hydroxyl group (1)
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 Perturbation (Quantum dynamics) (1)
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 Fission products  Computer programs<br />Neutron flux  Measurement<br />Neutron irradiation  Measurement (1)
Articles 1  18 of 18
FullText Articles in Nuclear Engineering
Application Of Invariant Imbedding To Radiation Transport Theory , John Lou Ridihalgh
Application Of Invariant Imbedding To Radiation Transport Theory , John Lou Ridihalgh
Retrospective Theses and Dissertations
No abstract provided.
Investigation By Neutron Diffraction Utilizing White Neutron Radiation, Arlen Ray Schade
Investigation By Neutron Diffraction Utilizing White Neutron Radiation, Arlen Ray Schade
Doctoral Dissertations
"The most probable reactor core neutron velocity was determined by analysis of data obtained from single crystals of copper and lithium fluoride. Derivation of the relationship between the maximum in experimental count rate and the most probable velocity, an error analysis of the method, and the computer routine are given for the method used to obtain the most probable velocity. The most probable velocity was used to index the maxwellian distributions from polycrystalline materials. Investigations were done with white neutron radiation of various silicon steel samples of different preferred orientation. A method is described by which the preferred orientation of ...
The Design Of A Molten Fueled, Vortex Reactor, For Use As A Rocket Propulsion Device, Robert Philip Schmitt
The Design Of A Molten Fueled, Vortex Reactor, For Use As A Rocket Propulsion Device, Robert Philip Schmitt
Masters Theses
"The purpose of this investigation is to design a nuclear reactor which can be used as a rocket propulsion device. The reactor investigated is fueled with a molten uraniumbismuth alloy and utilizes a two phase vortex flow principle. Hydrogen is employed as a coolant and rocket propellant. The hydrogen is heated directly by the fuel thus eliminating the need for heat exchangers. The major part of the investigation consists of a two group neutron diffusion study to show the operational feasibility of this type of reactor and to obtain an optimum design. the study shows that this type of reactor ...
Semiempirical Determination Of The Differential Fast Flux Spectrum For U235 Fission With Water Moderator, Henry Anthony Till
Semiempirical Determination Of The Differential Fast Flux Spectrum For U235 Fission With Water Moderator, Henry Anthony Till
Masters Theses
"The differential fast flux spectrum of the UMR Pool Research and Training Reactor core was determined by simultaneous activations of threshold foil detectors by neutronnucleon reactions. This represents one phase of the composite neutron environment at two sample irradiation locations and the center of a fuel element during a power operation of 200 Kw (th). To accomplish this measurement a semiempirical leastsquares approximation fitting activation date to a theoretical Cranberg Uwet fission spectrum was applied. This is a technique designed specifically for water moderated systems and takes into consideration both virgin and downscatter neutrons. Gamma decay photopeaks were reduced using ...
Computer Simulation Of Radiation Damage In Fe₃Al, Roland Otto Jackson
Computer Simulation Of Radiation Damage In Fe₃Al, Roland Otto Jackson
Masters Theses
"A computer program, designed to simulate the ordered state of the B.C.C. alloy, Fe₃Al, was used to study the effects of irradiation on an orderdisorder alloy. Twentysix runs were made with this program representing a variety of initial conditions. In all cases, the final damaged state consisted of Frenkel defects, vacancyinterstitial pairs; and the distance separating these pairs was a sensitive function of the energy and direction imparted to the primary knockon. Both the vacancy and the interstitial were found to be normal, stable defects, with the interstitial residing in a "split"configuration oriented in the [110] direction ...
The Decomposition Of 5Hydroxymethyl2Furaldehyde Under Gamma Irradiation, William George Bowles
The Decomposition Of 5Hydroxymethyl2Furaldehyde Under Gamma Irradiation, William George Bowles
Masters Theses
"An investigation into the effects of gamma irradiation decomposition of 5hydroxymethyl2furaldehyde (HMF) revealed HMF to be resistant to radiation catalyzed decomposition. A 1.0 normal solution of HMF was irradiated at a dose rate of 4.1 x 10⁵ Rads/hr to a total dose of 8.2 x 10⁶ Rads from a 5000 Curie ⁶⁰Co source. a total of 31 per cent of the HMF decomposed in a zero order reaction, although it was found the HMF decomposed completely under cadmium shielded irradiation in a nuclear reactor with some neutrons present. The reaction rate constant was found to be ...
Fast Neutron Induced Resistivity Changes In OrderDisorder Fe₃Al, Bruce A. Betts
Fast Neutron Induced Resistivity Changes In OrderDisorder Fe₃Al, Bruce A. Betts
Masters Theses
"Resistivity measurements were made of ordered, disordered and intermediate states of orderdisordered specimens of Fe₃Al while being irradiated by neutrons. All the specimens were irradiated at ambient temperature, approximately 35°C in a modified Bulk Shielding Swimming Pool type reactor. The ordered and near ordered specimens increased in resistivity indicating disordering whereas the disordered and near disordered specimens decreased in resistivity indicating an ordering process was occuring [sic]. By extrapolation, an equilibrium condition was determined and estimated at 130135 microohmscm resistivity that would remain constant during irradiation because the ordering and disordering affects of neutron irradiation would be in equilibrium ...
Design And Construction Of A Liquid Nitrogen Cryostat For Use In A Swimming Pool Type Reactor, Bruce B. Joiner
Design And Construction Of A Liquid Nitrogen Cryostat For Use In A Swimming Pool Type Reactor, Bruce B. Joiner
Masters Theses
"The continued expansion of the nuclear reactor facility and the nuclear engineering program dictates the need that a liquid nitrogen cooled cryostat be available at the reactor. This unit would be available for use in graduate and undergraduate laboratories and for graduate research. A liquid nitrogen cooled cryostat capable of maintaining a sample between 77°K to 80°K for an extended period of time in or adjacent to the core of the reactor was designed, constructed, and successfully operated. Recommendations were made for possible modifications to expand the versatility of the system"Abstract, page ii.
Zap  A Computer Program To Predict Fission Product Concentrations As A Function Of Neutron Flux, Irradiation And Cooling Times, Bruce Earl Koopmann
Zap  A Computer Program To Predict Fission Product Concentrations As A Function Of Neutron Flux, Irradiation And Cooling Times, Bruce Earl Koopmann
Masters Theses
"The development of a computer code was undertaken to calculate the fission product nuclide concentration for spent fuel discharged from a nuclear reactor, as a function of irradiation time, cooling time, neutron flux, and element cross section. The necessary input data was prepared from the basic nuclear data for fission of uranium235 and plutonium239. Calculations are also made for total or selective element beta heating and total gamma flux according to user selected input groups. These calculations would be useful in fuel element shielding, cooling, shipping and processing studies"Abstract, page ii.
GammaIrradiation Effects In SingleCrystalline Barium Titanate , John Joseph Keating
GammaIrradiation Effects In SingleCrystalline Barium Titanate , John Joseph Keating
Retrospective Theses and Dissertations
No abstract provided.
Applications Of The Transmission Matrix Method To Neutron And Gamma Transport , Ervin Thomas Boulette
Applications Of The Transmission Matrix Method To Neutron And Gamma Transport , Ervin Thomas Boulette
Retrospective Theses and Dissertations
No abstract provided.
Spatially Dependent Frequency Response Of Coupled Core Reactors , Ira Wilson Merritt Jr.
Spatially Dependent Frequency Response Of Coupled Core Reactors , Ira Wilson Merritt Jr.
Retrospective Theses and Dissertations
No abstract provided.
Electron Transport Theory Using Methods Of Invariant Imbedding , Robert Jay Barrett
Electron Transport Theory Using Methods Of Invariant Imbedding , Robert Jay Barrett
Retrospective Theses and Dissertations
No abstract provided.
Neutron Activation Analysis Applied To Arsenic Determination , Bong Kyu Lee
Neutron Activation Analysis Applied To Arsenic Determination , Bong Kyu Lee
Retrospective Theses and Dissertations
No abstract provided.
Analysis Of Coupled Core Reactors Using The Natural Mode Approximation , Joaquin Manuel Betancourt
Analysis Of Coupled Core Reactors Using The Natural Mode Approximation , Joaquin Manuel Betancourt
Retrospective Theses and Dissertations
No abstract provided.
The Effect Of Gamma Radiation On The Conductivity Of Sodium Chloride , Michael Claudewell Jon Carlson
The Effect Of Gamma Radiation On The Conductivity Of Sodium Chloride , Michael Claudewell Jon Carlson
Retrospective Theses and Dissertations
No abstract provided.
Solution Of The SpaceTime Dependent Neutron Kinetics Equations For A Reflected Slab Reactor , James Hugh Mcfadden
Solution Of The SpaceTime Dependent Neutron Kinetics Equations For A Reflected Slab Reactor , James Hugh Mcfadden
Retrospective Theses and Dissertations
No abstract provided.
Hamiltonian Formalism Applied To Multidimensional Reactor Systems And Related Concepts , Larry Charles Madsen
Hamiltonian Formalism Applied To Multidimensional Reactor Systems And Related Concepts , Larry Charles Madsen
Retrospective Theses and Dissertations
No abstract provided.