Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

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.
System: The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor (open access)

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.
System: The UNT Digital Library
Final Design Report: DR-1 Gas Loop (open access)

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.
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G (open access)

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.
System: The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1 (open access)

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.
System: The UNT Digital Library