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Full-Text Articles in Engineering

The Effects Of Washout In Polydispersed Metalic Aerosols, Jerry N. Burford Jan 1974

The Effects Of Washout In Polydispersed Metalic Aerosols, Jerry N. Burford

Masters Theses

"Experimental Collection Efficiencies are presented for drops of approximately 0.1cm radius falling through aluminium, magnesium and molybdenum oxide polydispersed aerosols. The experimentation was conducted in two identical cylindrical chambers, one being used for aerosol washout, and the other for allowing the aerosol to decay normally. The Collection Efficiency data were thus determined by comparing the aerosol concentration changes in the two chambers. The rather strong effects that induced micro-turbulence and relative humidity have on aerosol collection and aerosol decay were observed and are discussed"--Abstract, page ii.


Reliability Analysis Of The University Of Missouri--Rolla Reactor, Jimmy Dale Schottel Jan 1974

Reliability Analysis Of The University Of Missouri--Rolla Reactor, Jimmy Dale Schottel

Masters Theses

"The reliability of Nuclear Installations is becoming an important area of research. In this report an approach to reliability analysis was made. The actual failure data was utilized to predict theoretical failure distributions. These distributions were then used to determine future reliability of components, subsystems and system"--Abstract, p. ii


Calculation Of The Neutron Flux In The Side Regions Of The Prestressed Concrete Reactor Vessel Of A High Temperature Gas Cooled Reactor, Richard Robert Kent Jr. Jan 1974

Calculation Of The Neutron Flux In The Side Regions Of The Prestressed Concrete Reactor Vessel Of A High Temperature Gas Cooled Reactor, Richard Robert Kent Jr.

Masters Theses

"Neutron flux in the side regions of the High Temperature Gas Cooled Reactor's (HTGR) Prestressed Concrete Reactor Vessel (PCRV) was determined using the Monte Carlo method. One quarter of the PCRV was modeled, with all major structures inside it, e.g. steam generator, auxiliary cooling loop, etc. imaged at their exact position and size. Initial neutron energies range from .001 eV to 3 MeV. Three neutron interactions were considered: absorbtion, elastic scattering, and inelastic scattering.

The flux was calculated for two different PCRV temperatures, 155° F and 647° F. The thermal flux showed a minor increase at the higher temperature. In …


Waste Heat Utilization From A Direct Cycle High Temperature Gas Cooled Nuclear Reactor For District Heating And Air Conditioning, John Joseph Blase Jan 1974

Waste Heat Utilization From A Direct Cycle High Temperature Gas Cooled Nuclear Reactor For District Heating And Air Conditioning, John Joseph Blase

Masters Theses

"An analysis was conducted to determine the economic as well as technical feasibility of waste heat utilization from the proposed direct cycle high temperature gas cooled nuclear reactor, as designed by the General Atomic Company.

The rejected heat from this system is at considerably higher temperatures than those normally encountered in conventional steam-electric Rankine cycles. By taking advantage of these higher rejection temperatures, heat was translated into energy available to a district heating and air conditioning service. The transportation of this energy was considered to be in the form of heated and chilled water.

A refrigeration capacity on the order …


Possible Damage Mechanism In Dresden 2 Class Boiling Water Reactor Fuel, Donald Lee Moffett Jan 1974

Possible Damage Mechanism In Dresden 2 Class Boiling Water Reactor Fuel, Donald Lee Moffett

Masters Theses

"A thermal hydraulic analysis of a typical hot channel of a Dresden 2 class boiling water reactor is studied for possible severe local overheating. The COBRA-II thermal hydraulic analysis code is modified to include critical heat flux calculations for each subchannel. The effects of flow distribution, inlet mass velocity variations, dimensional tolerances, enrichment variations, and input parameters are examined in detail. Bulk channel results are in good agreement with the published data, but the assembly wall side of the corner fuel rod has a minimum critical heat flux ratio of less than unity for a number of the situations examined. …


Post Irradiation Changes Of The Elastic Modulus Of Aluminum, Dale A. Powers Jan 1974

Post Irradiation Changes Of The Elastic Modulus Of Aluminum, Dale A. Powers

Masters Theses

"Aluminum samples of 99.99% and 99.999% purity were irradiated to neutron fluences of 3·8·1018 nvt and 1.4·1019 nvt (E greater than 0.1 Mev) at one-third of the melting temperature. The change in Young's modulus of elasticity after isothermal annealing in the temperature range of 110⁰C to 130⁰C was measured. After 2.5 hours of annealing, the modulus reached a steady state value which was decreased by 0.25% ± 0.17% from the unannealed value. Electron microscopy suggests the hardening mechanisms were dispersion hardening by silicon precipitates and void hardening"--Abstract, page ii.