Nuclear Engineering Commons^™

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.

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

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 …

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.