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Articles 1 - 9 of 9

Full-Text Articles in Nuclear Engineering

Elastic-Plastic Poisson's Ratio Of Borsic-Reinforced Aluminium Composites, Ronald Edward Allred Dec 1972

Elastic-Plastic Poisson's Ratio Of Borsic-Reinforced Aluminium Composites, Ronald Edward Allred

Nuclear Engineering ETDs

Poisson's ratio as a function of tensile strain has been examined for four volume fractions of unidirectional Borsic-reinforced aluminum composites. Linear relationships were found between Poisson's ratio and fiber volume fraction during Stage I (elastic filaments-elastic matrix) and Stage II (elastic filaments-plastic matrix) deformation which confirms that rule-of-mixtures equations may be used to predict Poisson's ratios for metal-matrix composites. These equations must be used with care, however, due to differences in the Poisson's ratio behavior of the components of the composite when tested alone and in situ in the composite. These differences are attributed to the ...


Analysis Of Radiation From A Line Source Using The Transmission Matrix Method , Hiroshi Hiranuma Jan 1972

Analysis Of Radiation From A Line Source Using The Transmission Matrix Method , Hiroshi Hiranuma

Retrospective Theses and Dissertations

No abstract provided.


Experimental Study Of Neutron Reflection From A Cylindrical Surface, Dale Lee Holtzscher Jan 1972

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 Jan 1972

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 ...


Use Of Isotopes To Reduce Neutron-Induced Radioactivity And Augment Thermal Quality Of The Environment Of An Underground Nuclear Explosion, Nathaniel Fred Colby Jan 1972

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 ...


Containment Systems For Storage Of Solidified High-Level Radioactive Wastes In Bedded Salt Deposits , Terence Joseph Sullivan Jan 1972

Containment Systems For Storage Of Solidified High-Level Radioactive Wastes In Bedded Salt Deposits , Terence Joseph Sullivan

Retrospective Theses and Dissertations

No abstract provided.


Prediction Of Heated Effluent Dispersion In A Stream Using Similitude Techniques , Max Myron Delong Jan 1972

Prediction Of Heated Effluent Dispersion In A Stream Using Similitude Techniques , Max Myron Delong

Retrospective Theses and Dissertations

No abstract provided.


Computer Simulation Of The Primary Recoil Spectra And Damage Cross Section Of Fe₃Al Using Endf/B Ii Data, Daniel Willard Smith Jan 1972

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 ...


Performance Characteristics For Optimized Core Module Of Liquid Metal Fast Breeder Reactor , Satoshi Minakuchi Jan 1972

Performance Characteristics For Optimized Core Module Of Liquid Metal Fast Breeder Reactor , Satoshi Minakuchi

Retrospective Theses and Dissertations

No abstract provided.