Serial/Series Title
12 Matching Results
Results open in a new window/tab.
Results:
1 - 12 of
12
Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963
From abstract: The concept of using high intensity beta radiation from an isotopic source, Sr-90, inside a high temperature, high pressure chemical reactor has been developed for potential radiation chemical processes. Distinct advantages include high utilizable intensity from a relatively small source with a minimum of shielding against external radiation.
Date:
September 11, 1964
Creator:
Yavorsky, P. M. & Gorin, E.
System:
The UNT Digital Library
A Study of Desalting Plants (15 to 150 mgd) and Nuclear Power Plants (200 to 1500 MWt) for Combined Water and Power Production: Final Report
From foreword: This study is concerned with the technology of producing fresh potable water from the seas.
Date:
September 1964
Creator:
Catalytic Construction Company
System:
The UNT Digital Library
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows
From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date:
September 15, 1964
Creator:
Winborne, R. A.
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964
From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date:
September 15, 1964
Creator:
Darley, D. K.
System:
The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date:
September 1964
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers
Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date:
September 1964
Creator:
Stein, Ralph P.
System:
The UNT Digital Library
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date:
September 1, 1964
Creator:
Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
System:
The UNT Digital Library
6144-Channel Time-of-Flight Analyzer
Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
System:
The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date:
September 1964
Creator:
Benham, R. D. & Wilburn, N. P.
System:
The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies
Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date:
September 1964
Creator:
Allemann, R. T.; Roberts, F. P. & Upson, U. L.
System:
The UNT Digital Library
Gas-Cooled Fast Reactor Concepts
Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date:
September 1964
Creator:
Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
System:
The UNT Digital Library
The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2
Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date:
September 1964
Creator:
Helm, J. W.
System:
The UNT Digital Library