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Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.

Date: June 1961

Creator: Muraoka, J.

Partner: UNT Libraries Government Documents Department

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The Thermal Hydraulics Laboratory at Hanford

Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.

Date: November 1961

Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.

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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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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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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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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Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.

Date: April 1961

Creator: Koler, R. K.

Partner: UNT Libraries Government Documents Department

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Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.

Date: June 1961

Creator: Todd, R. H.

Partner: UNT Libraries Government Documents Department

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The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.

Date: July 1961

Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.

Partner: UNT Libraries Government Documents Department

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Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.

Date: March 1961

Creator: Sharp, R. E.

Partner: UNT Libraries Government Documents Department

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Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

The Thermal Hydraulics Laboratory at Hanford

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

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

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

Final Design Report: DR-1 Gas Loop

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

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H