68 Matching Results

Search Results

Results: 1 - 24 next
open access

Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV

Description: Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nu… more
Date: March 30, 1961
Creator: Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Port Survey of the State of New York

Description: Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date: November 1961
Creator: Ebasco Services Incorporated
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960

Description: From abstract: This report describes analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed.
Date: July 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mechanical Properties of Zircaloy-2

Description: Abstract: The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrogen content, and the presence or absence of a notch.
Date: February 1, 1961
Creator: Mehan, R. L. & Wiesinger, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

Description: "An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date: July 30, 1961
Creator: Gehman, William G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F

Description: Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date: February 28, 1961
Creator: McDonald, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen