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Progress Report for SNAP 4: July-September 1961

Description: Report describing the program objectives, program summary, summary developments status, development system (critical assembly), and component development progress (fuel) for Systems for Nuclear Auxiliary Power (SNAP) 4, a multipurpose compact nuclear power system, for the period July to September 1961.
Date: December 15, 1961
Creator: Flower, L. M.
Partner: UNT Libraries Government Documents Department
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SRE-PEP Moderator Elements: Final Report

Description: Report discussing the design and engineering of the new Zircaoloy-2 moderator and reflector elements for the Solid Reactor Experiment (SRE) Power Expansion Program (PEP). The existing design, proposed design, and details of the final design are described. Additional aspects described include are material properties, thermal analysis, stress analysis, and the final proof test.
Date: January 15, 1966
Creator: Jones, C. E.
Partner: UNT Libraries Government Documents Department
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Multiple-Unit SNAP 2 Power Systems for Manned Application

Description: Report describing a study made of the feasibility of utilizing multiple-unit Systems for Nuclear Auxiliary Power (SNAP) 2 systems to provide power in the 10- to 40-kwe range for manned space stations. Reliability, packaging, weight, operational considerations are discussed. (Abstract)
Date: January 28, 1964
Creator: Rosenberg, H. N.
Partner: UNT Libraries Government Documents Department
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Preliminary SNAPSHOT-1 Performance Summary

Description: Report presenting the preliminary evaluation test results from the Space Nuclear Auxiliary Power Shot (SNAPSHOT) flight test, launched in April 3, 1965. A flight test description, discussion of the data system, test results, description of system shutdown, and identification of technology gained from the Systems for Nuclear Auxiliary Power (SNAP) 10A flight test are included.
Date: August 1, 1965
Creator: Galantine, R. M.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date: March 15, 1957
Creator: Trilling, C. A.
Partner: UNT Libraries Government Documents Department
open access

Organic Moderated Reactor Experiment Progress Report: August-October 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
Partner: UNT Libraries Government Documents Department
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: December 15, 1964
Creator: Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: July 15, 1964
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
open access

Numerical Computation of Neutron Distribution and Critical Size

Description: Report presenting a numerical calculation, by diffusion theory, of the critical size of a nuclear reactor, and of the time dependent distribution of neutrons in the reactor as a function of position (one-dimensional space) and neutron energy. The mathematical development of the numerical method, properties of the equations, and procedure are discussed in the report, along with a numerical example.
Date: February 15, 1950
Creator: Thompson, A. Stanley
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
open access

OMR Control-Safety Rod Component Development Tests

Description: Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
Partner: UNT Libraries Government Documents Department
open access

Reactivity Absorbed by Xenon-135 in the SRE

Description: Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date: January 28, 1960
Creator: Woodruff, R. W.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Test of Natural-Circulation Double-Tube Steam Generator

Description: Abstract: Testing of the Natural Circulation Steam Generator has been conducted with the Sodium Reactor Experiment. A necessary modification of the original feed-water control system was utilized.
Date: December 1, 1959
Creator: Welsh, R. D.
Partner: UNT Libraries Government Documents Department
open access

Development of a Fuel Handling System for an Organic Moderated Reactor

Description: Abstract: This report describes the features of several systems which were rejected as inadequate, and the evaluation of a design leading to the construction of a prototype cask and its associated equipment.
Date: 1959
Creator: Leppard, J. A.
Partner: UNT Libraries Government Documents Department
open access

OMR Degasifier Loop Experiment

Description: Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
Partner: UNT Libraries Government Documents Department
open access

OMRE Fuel Plate Surface Temperature Measurement

Description: Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Partner: UNT Libraries Government Documents Department
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