Open Access. Powered by Scholars. Published by Universities.®

Nuclear Engineering Commons

Open Access. Powered by Scholars. Published by Universities.®

Articles 1 - 7 of 7

Full-Text Articles in Nuclear Engineering

Zap - A Computer Program To Predict Fission Product Concentrations As A Function Of Neutron Flux, Irradiation And Cooling Times, Bruce Earl Koopmann Jan 1968

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 uranium-235 and plutonium-239. 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.


Semiempirical Determination Of The Differential Fast Flux Spectrum For U-235 Fission With Water Moderator, Henry Anthony Till Jan 1968

Semiempirical Determination Of The Differential Fast Flux Spectrum For U-235 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 neutron-nucleon 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 least-squares approximation fitting activation date to a theoretical Cranberg U-wet fission spectrum was applied. This is a technique designed specifically for water moderated systems and takes into consideration both virgin and down-scatter neutrons. Gamma decay photopeaks were reduced using ...


Fast Neutron Induced Resistivity Changes In Order-Disorder Fe₃Al, Bruce A. Betts Jan 1968

Fast Neutron Induced Resistivity Changes In Order-Disorder Fe₃Al, Bruce A. Betts

Masters Theses

"Resistivity measurements were made of ordered, disordered and intermediate states of order-disordered 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 130-135 micro-ohms-cm 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 Jan 1968

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.


The Decomposition Of 5-Hydroxymethyl-2-Furaldehyde Under Gamma Irradiation, William George Bowles Jan 1968

The Decomposition Of 5-Hydroxymethyl-2-Furaldehyde Under Gamma Irradiation, William George Bowles

Masters Theses

"An investigation into the effects of gamma irradiation decomposition of 5-hydroxymethyl-2-furaldehyde (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 ...


Computer Simulation Of Radiation Damage In Fe₃Al, Roland Otto Jackson Jan 1968

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 order-disorder alloy. Twenty-six runs were made with this program representing a variety of initial conditions. In all cases, the final damaged state consisted of Frenkel defects, vacancy-interstitial pairs; and the distance separating these pairs was a sensitive function of the energy and direction imparted to the primary knock-on. 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 Design Of A Molten Fueled, Vortex Reactor, For Use As A Rocket Propulsion Device, Robert Philip Schmitt Jan 1968

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 uranium-bismuth 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 ...