Serial/Series Title
Country
States
19 Matching Results
Results open in a new window/tab.
Results:
1 - 19 of
19
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961
Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
Date:
August 10, 1961
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
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
Thermonuclear Division Semiannual Progress Report, January 31, 1961
Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.
Date:
May 31, 1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
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
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
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.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 22, 1961
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
Interim Report on Corrosion by Zirconium-Base Fluorides
Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date:
January 17, 1961
Creator:
Adamson, G. M.; Crouse, R. S. & Manly, W. D.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel
Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
Date:
1961
Creator:
Goode, J. H. & Flanary, J. R.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library