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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.

Date: November 1, 1961

Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.

Partner: UNT Libraries Government Documents Department

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Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.

Date: October 31, 1961

Creator: Oak Ridge National Laboratory. Health Physics Division.

Partner: UNT Libraries Government Documents Department

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Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)

Date: October 14, 1961

Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.

Partner: UNT Libraries Government Documents Department

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Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.

Date: September 21, 1961

Creator: Oak Ridge National Laboratory. Chemical Technology Division.

Partner: UNT Libraries Government Documents Department

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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.

Date: September 1961

Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.

Partner: UNT Libraries Government Documents Department

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Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Date: June 27, 1961

Creator: Oak Ridge National Laboratory

Partner: UNT Libraries Government Documents Department

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Engineering Test Reactor Critical Facility Control System Manual

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).

Date: June 23, 1961

Creator: Meichle, F. A.

Partner: UNT Libraries Government Documents Department

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Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

Date: June 1961

Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.

Partner: UNT Libraries Government Documents Department

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

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.

Partner: UNT Libraries Government Documents Department

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The Cold Pressing of Sinterable UO₂

The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.

Date: March 27, 1961

Creator: Levey, R. P., Jr.

Partner: UNT Libraries Government Documents Department

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Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

Date: March 1961

Creator: Baars, R. E.

Partner: UNT Libraries Government Documents Department

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Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).

Date: March 1961

Creator: Freshley, M. D.

Partner: UNT Libraries Government Documents Department

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Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

Date: February 3, 1961

Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.

Partner: UNT Libraries Government Documents Department

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Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).

Date: February 1961

Creator: Pessl, H. J.

Partner: UNT Libraries Government Documents Department

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Analytical Chemistry Division Annual Progress Report, December 31, 1960

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.

Date: 1961

Creator: Oak Ridge National Laboratory

Partner: UNT Libraries Government Documents Department

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Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.

Date: 1961

Creator: Evans, R. B., III; Truitt, J. & Watson, G. M.

Partner: UNT Libraries Government Documents Department

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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

Health Physics Division Annual Progress Report, July 31, 1961

Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Chemical Technology Division Annual Progress Report, May 31, 1961

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Engineering Test Reactor Critical Facility Control System Manual

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

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

The Cold Pressing of Sinterable UO₂

Final Design Report: DR-1 Gas Loop

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Analytical Chemistry Division Annual Progress Report, December 31, 1960

Superposition of Forced and Diffusive Flow in a Large-Pore Graphite