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Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho: Appendix 2, Basic Hydrologic Data
Graphs and tables summarizing detailed discharge data of the Big Lost River.
Date:
1960
Creator:
Nace, Raymond L.; Deutsch, Morris; Voegeli, Paul T.; Stewart, J. W.; Walton, William Clarence; Fowler, K. H. et al.
System:
The UNT Digital Library
Steam Generators for High-Temperature Gas-Cooled Reactors
Report describing a study that "was undertaken to provide a sound basis both for the optimization of either axial-flow or cross flow steam generators and for the evaluation of the relative merits of major design features" (p. 2).
Date:
1963
Creator:
Fraas, Arthur P. & Ozisik, M. N.
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
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
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.
System:
The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water
From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date:
April 15, 1965
Creator:
Nelson, R. William
System:
The UNT Digital Library
Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program
The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.
Date:
May 20, 1964
Creator:
Nelson, R. William
System:
The UNT Digital Library
Heat Transfer Reactor Experiment Number 3: Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program
From abstract: "Describes Heat Transfer Reactor Experiment No. 3, a solid-moderated nuclear power plant with a horizontal reactor."
Date:
June 15, 1962
Creator:
Linn, F. C.
System:
The UNT Digital Library