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 Nuclear reactorsShielding (Radiation) (1)
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 Radioactive waste disposal<br />Rhodium  Isotopes<br />Technetium  Isotopes<br />Underground nuclear explosions (1)
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 Liquid metal cooled reactors (1)
 Lakes (1)
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Articles 1  9 of 9
FullText Articles in Nuclear Engineering
ElasticPlastic Poisson's Ratio Of BorsicReinforced Aluminium Composites, Ronald Edward Allred
ElasticPlastic Poisson's Ratio Of BorsicReinforced 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 Borsicreinforced aluminum composites. Linear relationships were found between Poisson's ratio and fiber volume fraction during Stage I (elastic filamentselastic matrix) and Stage II (elastic filamentsplastic matrix) deformation which confirms that ruleofmixtures equations may be used to predict Poisson's ratios for metalmatrix 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
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
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
Calculation Of Buildup Factors For Multilayer Slab Shields Using The Monte Carlo Method, John Paul Kuspa
Masters Theses
"Gammaray 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 NeutronInduced Radioactivity And Augment Thermal Quality Of The Environment Of An Underground Nuclear Explosion, Nathaniel Fred Colby
Use Of Isotopes To Reduce NeutronInduced 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 neutroninduced 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 halflives. Subsequent rapid decay will prolong the high temperature in the vicinity of the explosion and decrease the activity. Longlived isotopes created by neutron capture in the host rock would be minimized. The investigation is conducted for strontium90, cesium137, cerium144, technetium99, rhodium103 and 105. Of these, the first three appear to ...
Containment Systems For Storage Of Solidified HighLevel Radioactive Wastes In Bedded Salt Deposits , Terence Joseph Sullivan
Containment Systems For Storage Of Solidified HighLevel 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
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
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 energyexchange kernels which delineate the energy transfer probabilities between neutrons and Fe_{3}Al 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 energyexchange 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
Performance Characteristics For Optimized Core Module Of Liquid Metal Fast Breeder Reactor , Satoshi Minakuchi
Retrospective Theses and Dissertations
No abstract provided.