Search Results

open access

Nuclear Powered Tanker Design and Economic Analysis - Direct Cycle Boiling Water Reactor

Description: A design and economic analysis is presented for a 44,000 DWT tanker utilizing a 27,300 shp direct cycle boiling water reactor propulsion system. Included are design descriptions and drawings, estimates of operating and capitol costs for the reference ship, estimates of long range potential, descriptions of required research and development programs, a preliminary safeguards analysis, an analysis of ship's motion on boiling water reactor performance, a summary reactor physics analysis, and a dis… more
Date: December 15, 1959
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Some Control Rod Applications and Operating Experience in Power Reactor Environments

Description: Information obtained in a survey of control rod applications and operating experience is reported. This survey covered the Army Nuclear Power Program, the Organic Moderated Reactor Experiment, the Yankee Atomic Power Plant, the Shippingport Pressurized Water Reactor and the Argonne Experimental Boiling Water Reactor.
Date: December 14, 1960
Creator: Williamson, H.E.
Partner: UNT Libraries Government Documents Department
open access

Bounce III

Description: BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date: December 15, 1960
Creator: Kerr, B. A.
Partner: UNT Libraries Government Documents Department
open access

Prediction of Two-Phase Flow From Mixing Length Theory

Description: It is proposed in this report to describe a new two-phase flow mixing length model. It consists of treating the two-phase system as a continuous medium and applying to it the methods and assumptions so widely accepted in single-phase turbulent flow. Because it reduces a two-phase problem to an equivalent one in single-phase flow, the proposed model can be readily used to predict the effects of flow rate, channel geometry, and channel direction in two-phase flow.
Date: December 27, 1960
Creator: Levy, S.
Partner: UNT Libraries Government Documents Department
open access

Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)

Description: The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: December 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen