UNT Libraries Government Documents Department - 13 Matching Results

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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

High Power Density Development Project (Contract Pending) Advance Requisition 474-49976 - Second Quarterly Progress Report, July-September, 1960

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. It will be achieved by extensive development and testing carried out in conjunction with the design, construction and operation of the Big Rock Point plant of the Consumers Power Company in Michigan. This second quarterly report describes the progress achieved from July through September 1960.
Date: October 1, 1960
Creator: Holland, L. K.
Item Type: Refine your search to only Report
open access

Fuel Cycle Program: A Boiling Water Reactor Research and Development Program - First Summary Report, March 1959-July 1960

Description: The Fuel Cycle Development Program is a basic development program of boiling and other water reactor technology. This is the first report to the U.S. Atomic Energy Commission of activities carried out under this program. It constitutes a review of the progress from April 27, 1959 through July 31, 1960.
Date: 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
open access

Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker

Description: The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date: August 8, 1960
Creator: Biglieri, N. J.
Item Type: Refine your search to only Report
open access

Preliminary Report: 300 KWe Capsule Nuclear Power Plant Study

Description: This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.
Date: June 30, 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
open access

Final Report Chicago Operations Office Steam Separation Program, February-March, 1960

Description: A program of free-surface steam-water separation at 600 psig was carried out in support of the design for operation of the Experimental Boiling Water Reactor at 100 MW thermal. Reduced test data are presented without evaluation since the ANL technical representative received an original copy of the data for evaluation with respect to the EBWR design.
Date: 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
open access

VARI Solution of Simultaneous, First-Order, Ordinary, Differential Equations

Description: VARI solves on the IBM-650 a system of simultaneous, first-order, ordinary, differential equations. The program was written so that a large number of calculations could be done in a reasonable length of time. The program permits the consideration of the production of the isotope by absorption and/or decay of one or more of any of the other isotopes in the chain.
Date: March 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
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