Engineering Commons^™

Alternate Energy Removal Modes For Nuclear Power Reactors, Robert L. Carter

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

Attention is focussed upon the unique qualities of high energy fission particles, and upon the fundamental limits to the direct removal of their kinetic energy by electrostatic means and by cyclotron resonance deceleration. Efficiencies of secondary and tertiary product ionization and excitation produced by fission particles are examined. The potential for delivery of power through various non-thermal modes is discussed, and the significant unknowns relating thereto are identified.

Prospects For Nuclear Fusion Power, William C. Gough

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

The prospects for fusion power are discussed including the need for fusion, its environmental advantages, and the research results that form the basis for present confidence that the program will succeed. The steps remaining before commercial fusion power will be available are outlined. Exploratory ideas for second generation fusion electric power plants, and non electrical applications of fusion technology and reactors are briefly covered.

Are Nuclear Shipments Really Safe?, William A. Brobst

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

The transportation of nuclear materials is on the increase. Although nuclear shipments are only a very small fraction of the Nation’s hazardous materials shipments, they attract a great deal of public attention. Shipments of spent nuclear fuel and nuclear wastes are a particular concern.

One of the many fears that people have about nuclear energy is the possibility that a nuclear shipment might somehow go awry and cause a serious public hazard. Primarily, they are worried that a shipment of spent reactor fuel or highly radioactive waste could be involved in a serious rail or highway accident and dump its …

The Assessment Of Environmental Impacts At Nuclear Power Generating Stations, Thomas H. Row, J. R. Mcwherter

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

The Federal actions that are required with regard to nuclear power stations are the granting of a construction permit and later the issuance of a license to operate the station. Since the Atomic Energy Commission (AEC) is responsible for these actions, the Commission is also responsible for preparation of an environmental statement on the proposed actions. The National Laboratories including the one at Oak Ridge are used as part of the staff in preparing the statements.

The staff makes an independent determination of the plant effluents and their dispersions. The impact of these and plant construction on the environment are …

1st Umr-Mec Conference On Energy Resources -- Entire Proceedings, University Of Missouri--Rolla

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

No abstract provided.

Radiation Testing Under Simulated Loca Conditions, Kenneth G. Mayhan, D. R. Edwards, W. F. Oberbeck, J. F. Montle

UMR-MEC Conference on Energy / UMR-DNR Conference on Energy

The purpose of this evaluation is to gather data to determine whether or not radiation during a simulated Loss of Coolant Accident would have any effect upon the coatings being used. Because of the concern in industry regarding the safety of nuclear power generating stations and the strong actions of the various environmentalist clubs and agencies clubs and agencies, the utilities have been required to prove the safety of the power facilities to extraordinary degrees before licensing can be obtained to operate. One of the areas regarding the safety is the necessity of proving that the coatings will remain intact …

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

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.

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 …

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. …

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 …

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.