Nuclear Engineering Commons^™

Direct Ac Generation From Solar Cell Arrays, Fernando L. Alvarado, Adel H. Eltimsahy

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

Results of the investigation of the performance of solar cells when directly coupled to a conventional three-phase power network are presented. This approach dissociates the electricity production problem from the electric energy storage problem. Extensive studies of the required power inverter are performed. Preliminary simulation results indicate that ac power outputs of better than 90% of the optimum cell power output can be easily achieved by means of a suitably controlled inverter, thereby justifying the elimination of dc loads or local dc electric energy storage devices. It is also shown that the controlling policy for the inverter must depend on …

Dynamic Simulation For Regional Energy Studies, B. W. Jones, P. M. Moretti, J. H. Mize

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

A series of models has been developed for regional studies of energy supply- demand systems. The models are based on dynamic simulation of components of the system using equations derived from the technical details of the system. The models contain sufficient detail to make in-depth studies and specific recommendations. The final goal is to include all aspects of regional energy systems from native supplies of energy resources to the economic activities of the region.

To develop a comprehensive model, the system has been partitioned into subsystems, so that a detailed model can be made for each subsystem. The detailed model …

How Might Synthetic Fuels From Coal Affect Natural Resources And Environment?, H. J. Plass Jr.

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

Energy self-sufficiency for the U. S. requires substantially increased use of coal. Direct combustion of coal without adequate environmental controls, as would occur if coal were used as a fuel for homes and offices throughout the country, would result in severe air pollution problems„ Synthetic fuels from coal such as methane, low BTU gas, or hydrogen, when utilized by the homes and businesses as gas or as electricity from gas, will contribute a much smaller amount of air pollution. However, to make these synthetic fuels available, it is necessary to mine more coal than would have to be mined for …

Alcohol Assisted Hydrocarbon Fuels: A Comparison Of Exhaust Emissions And Fuel Consumption Using Steady-State And Dynamic Engine Test Facilities, D. J. Bushnell, J. M. Simonsen

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

This paper presents experimental data which exemplifies the differences in emission level testing on internal combustion engines when dynamic engine tests are used instead of steady-state engine tests. A comparison of the two test methods is made using hydrocarbon fuels with varying amounts of methanol. Emissions measured include the nitric oxides, unburned hydrocarbons and carbon monoxide. Emission levels and fuel consumption are reported for the various volumetric percentages of methanol in the fuel.

Of special significance are the different trends the emission levels establish when subjected to a dynamic engine test as compared to the results for the steady-state tests. …

Computer Simulation Of Radiation Effects In Fe₃Al By Using Alternating Direction Implicit Numerical Techniques., Dean Lewis Tibbitts

Masters Theses

"An analysis was conducted to see if the alternating direction implicit (a.d.i.) numerical technique could be applied to a many-body dynamical radiation damage model.

The computer program which resulted was named ADI. It was numerically stable for small time steps used in conjunction with low ev knock-ens. It was also able to relax the a toms in the system simultaneously in the implicit direction. However, an existing explicit computer code, which was to be replaced by ADI, proved to be more numerically stable and about 40% faster"-- Abstract, p. ii

A Computer Technique For Calculating The Radiological Consequences Of Pressurized Water Reactor Power Plant Hypothetical Accidents, Charles Francis Gill

Doctoral Dissertations

"A closed form analytical method of calculating the radiological consequences of ten pressurized water reactor (PWR) hypothetical accidents was developed. This methodology was used to develop a computer code, DOSES, to compute the gamma-whole body, beta-skin and iodine inhalation thyroid doses at the site boundary, at the low population zone outer boundary and for control room occupancy for the ten PWR hypothetical accidents. The computer code, DOSES, was developed to operate in the conversational remote terminal mode and to provide a mechanism for producing required information for chapter 15 of PWR nuclear power plant safety analysis reports.

The identification of …

Effect Of Photoneutrons On Transients Of Beryllium Reflected Reactors, Safdar Ahmad Ali

Doctoral Dissertations

"An analytical model is developed to account for the photoneutron sources present in a beryllium reflector. The time-dependent, two- dimensional and three energy-group diffusion equations are written with an additional photoneutron source term. Then an approximate flux composed of two spatial shapes chosen beforehand, each having an unknown time coefficient, is inserted into time-dependent multigroup equations and the weighted residual criterion is applied. This yielded multimode kinetics equations with generalized definitions for conventional matrix parameters: generation time, reactivity, delayed neutron and delayed photoneutron fraction matrices.

Two transients are analyzed for the University of Missouri Research Reactor: simulation of rod drop …

Experimental Study Of Electron Density And Confinement Time In An Electrostatically-Plugged Cusp Device Using A Microwave Interferometer, Robert Louis Hayward

Masters Theses

"The average electron density and electron confinement time in an electrostatically plugged magnetic spindle cusp device are studied using a 20 GHz microwave interferometer. The results are compared with the predictions from approximate theoretical equations. With a magnetic induction in the point cusp of 5000 Gauss, a plasma is produced by injecting a 5 mA, 500 eV electron beam into hydrogen gas at 10^-5 Torr. The measured electron density is 2 x 10^-10 cm^-3 and the measured confinement time is 80 ysec, which agree to within a factor of two with values predicted by theory"--Abstract, page ii.

Energy, Environment And Incremental Decision Making, Jeff V. Conopask, Robert R. Reynolds Jr.

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

During the late 1960's and early 70's a variety of environmental/energy oriented legislation was enacted by the Congress. The most important of these acts, the National Environmental Protection Act (NEPA), required that environmental impact statements be filed when various private and public activities have a potential for impacting man and his environment. (17) Impact statement requirements go beyond the currently practiced cost/benefit analysis, which is often just a production (direct) impact assessment. Heretofore, indirect or second round economic and social effects of consequence affecting other national goals were seldom counted.

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.

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

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.

Feasibility Study Of An Electromagnetic Trap Fusion Reactor., Dennis Gilbert Blondin

Masters Theses

"Through the use of detailed particle and energy balances, electromagnetic traps with magnetic cusps are found to be unsatisfactory for continuous operation when using only neutral particle beams to sustain a thermonuclear plasma. Low power multiplication characteristics inherent in this CTR design probably preclude supplemental plasma heating methods. However, by using an alternate Yin-Yang magnetic system, continuous CTR operating regimes are found at an ion temperature of 20 keV while assuming only neutral particle beam heating. Although these regimes require applied electrostatic potentials approaching a half-million volts, this device demonstrates a capability for efficient power production"-- Abstract, p. ii

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.

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

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. …

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 …

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 …

Neutronics Calculations Of Two Fusion Reactor Blankets, James Edward Struve

Masters Theses

"At the present state of engineering development, the most probable fusion reactor fuel cycle will use deuterium and tritium in the reaction ²₁D + ³ ₁T → ¹₀n + ⁴₂He. This reaction is exothermic and provides 17.6 Mev of energy of which 14.1 Mev are given to the neutron. The reaction will take place in a plasma environment inside an evacuated chamber. This chamber will be surrounded by a "blanket" which will serve to transform the kinetic energy of the neutron into heat and produce tritium for subsequent use in the fuel cycle. …

Use Of Radioactive Iodine Evolved Into Reactor Cooling Water To Locate Defective Fuel Elements, Carl Mozel Stroud

Masters Theses

"The relative amount of radioactive iodine evolved in reactor cooling water by each fuel element provides an excellent indication of defective cladding on fuel elements. The radioactive iodine evolved into the reactor cooling water from a defective fuel element should be higher than the average radioactive iodine evolved by other fuel elements into the cooling water by an order of magnitude or more.

Radioactive iodine with non-radioactive iodine carrier is adsorbed on DOWEX SBR resin in the iodide form. The iodide is eluted from the resin with sodium hypochlorite and extracted into carbon tetrachloride. The iodine is reduced to iodide …

Break-Even Criteria For A Pulsed D-T Reactor, Kenneth Franklin Keller

Masters Theses

"To those who keep track of such things and are in a position to make predictions, it appears that the use of controlled thermonuclear reactions to economically produce electric power is well within a lifetime from now. Indeed, experiments presently being conducted are putting us closer and closer to the development and construction of demonstration fusion reactors. Understandably, the people working on such products and processes are optimistic about their results. This is as it should be if our nation is to avoid major energy shortages in the future.

Unfortunately, the tenor of this paper is pessimistic. This is not …

Calculation Of Gamma-Ray Albedo Using The Monte Carlo Method, Ezatholah Aslani-Amoli

Masters Theses

"Gamma-ray number, energy and dose albedo are calculated with the Monte Carlo technique. A plane monoenergetic beam was considered at normal incidence upon single material shields at initial gamma energy up to 10 MeV. Aluminum, iron and lead are used as shield material. The contribution of secondary photons which are produced as a result of various photon interactions in the shield are taken into account. These secondary photons are annihilation gammas, X rays and bremsstrahlung gammas. In certain cases, they constitute a considerable fraction of the reflected radiation.

Annihilation gammas predominate in the reflected radiation for all energies above 1.02 …

Use Of Isotopes To Reduce Neutron-Induced Radioactivity And Augment Thermal Quality Of The Environment Of An Underground Nuclear Explosion, Nathaniel Fred Colby

Masters Theses

"The use of isotopes to include radioactive waste products to reduce the neutron-induced activity of an underground nuclear explosion and its application in the field of geothermal power stimulation is discussed. A shield composed of selected isotopes surrounding a fusion device will capture excess neutrons producing isotopes with short half-lives. Subsequent rapid decay will prolong the high temperature in the vicinity of the explosion and decrease the activity. Long-lived isotopes created by neutron capture in the host rock would be minimized. The investigation is conducted for strontium-90, cesium-137, cerium-144, technetium-99, rhodium-103 and -105. Of these, the first three appear to …

Computer Simulation Of The Primary Recoil Spectra And Damage Cross Section Of Fe₃Al Using Endf/B Ii Data, Daniel Willard Smith

Masters Theses

"A computer program, using Evaluated Nuclear Data File (ENDF/B II) information, was used to develop energy-exchange kernels which delineate the energy transfer probabilities between neutrons and Fe₃Al lattice atoms. The kernels combine all available information on elastic and inelastic scattering contained in the ENDF/B II data.

The computer program used to generate the primary recoil spectra is SAKI, a modified version of RICE (1). SAKI is designed to calculate energy-exchange probabilities in any binary alloy as well as damage cross sections and optimum cutoff energies for use in comparing displacement effects in different reactor spectra."--Abstract, page ii.

Experimental Study Of Neutron Reflection From A Cylindrical Surface, Dale Lee Holtzscher

Masters Theses

"The reflection patterns for an elliptical neutron beam impinging upon cylindrical and planar surfaces were measured. The flux intensity as a function of distance from the surface of either planar or cylindrical reflectors decreased monotonously with distance. No "focusing" of the neutron beam appeared in the case of the cylindrical reflectors but the flux did not decrease as rapidly as in the planar case. For the elliptical neutron beam the experimentally determined neutron flux distribution agrees with calculation"--Abstract, page ii.

Calculation Of Buildup Factors For Multilayer Slab Shields Using The Monte Carlo Method, John Paul Kuspa

Masters Theses

"Gamma-ray beams normally incident upon slab shields of varying compositions are studied using a computer program based upon the Monte Carlo technique. Initial gamma energies of 1, 4, 6, and 8 MeV are considered. The shielding materials used were aluminum, iron, and lead. Both single and double material shields were investigated, at a variety of thicknesses up to a maximum of five mean free paths. Two secondary gamma processes are included in this simulation: annihilation gammas from pair production and bremsstrahlung from the electrons. The primary effort is the calculation of the dose, energy, and number buildup factors for these …