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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
ETR Nuclear Instrumentation : Final Report
Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date:
February 3, 1960
Creator:
Hanson, D. C.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
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 15, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Proposal for an Advanced Engineering Test Reactor : ETR II
Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date:
March 17, 1960
Creator:
deBoisblanc, D. R.
System:
The UNT Digital Library
Transportability Studies : ML-1 Nuclear Power Plant
Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.
Date:
April 1960
Creator:
Blakley, J. W.; Alcorn, J. S.; Del Valle, L. G.; Healy, P. W.; Moran, D. H. & Scott, W. S.
System:
The UNT Digital Library
The ML-1 Design Report
From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date:
May 16, 1960
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 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:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
In-Pile Tests of GCRE-IB Prototype Fuel Elements: Interim Report, 1958-1959
Interim report for the Army Gas-Cooled Reactor Systems Program, discussing various tests in a project to "develop and evaluate a ceramic-core, pin-type fuel element" (p. 1).
Date:
December 1960
Creator:
Watanabe, H. T.; Janne, J. E. & Wilson, W. D.
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
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date:
April 28, 1961
Creator:
Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
System:
The UNT Digital Library
Research and Development Studies on Waste Storage Process
Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date:
May 19, 1961
Creator:
Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
System:
The UNT Digital Library
Engineering Test Reactor Critical Facility Control System Manual
This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date:
June 23, 1961
Creator:
Meichle, F. A.
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 Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date:
September 8, 1961
Creator:
Porter, E. H.
System:
The UNT Digital Library
MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650
Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date:
1962
Creator:
Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
System:
The UNT Digital Library
Critical Path Scheduling of ETR and MTR Reactor Shutdowns
Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date:
January 10, 1962
Creator:
Jacobs, R. T. & Myers, L. L.
System:
The UNT Digital Library
Special Power Excursion Reactor Test III Pressurizer Vessel Failure
Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
Date:
January 29, 1962
Creator:
Heffner, R. E.; Wilson, T. R.; Halls, D. P.; Hickman, W. W. & Hoopingarner, K. R.
System:
The UNT Digital Library
Annual Progress Report on Fuel Element Development for Fiscal Year 1961
Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).
Date:
March 9, 1962
Creator:
Gibson, G. W. & Shupe, O. K.
System:
The UNT Digital Library
Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors
Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.
Date:
April 16, 1962
Creator:
Masterson, Richard G.
System:
The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date:
April 27, 1962
Creator:
Burn, P.
System:
The UNT Digital Library
Chemical and Physical Character of Ground Water in the National Reactor Testing Station, Idaho
Report documenting "the chemical and physical properties of the ground water beneath the National Reactor Testing Stations (NRTS), Idaho. The chemical properties described are chiefly the concentration and proportions of the dissolved constituents" (p. 1).
Date:
May 1962
Creator:
Olmsted, F. H.
System:
The UNT Digital Library
U.S. Atomic Energy Commission Idaho Operations Office Health and Safety Division Annual Report: 1961
Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
Date:
May 21, 1962
Creator:
U.S. Atomic Energy Commission. Idaho Operations Office.
System:
The UNT Digital Library
Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels
Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date:
June 20, 1962
Creator:
Chamberlain, H. V.
System:
The UNT Digital Library
Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor
The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.
Date:
July 1962
Creator:
Babcock & Wilcox Company. Atomic Energy Division.
System:
The UNT Digital Library