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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 UO₂ 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
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date:
August 17, 1962
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests
Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date:
October 19, 1962
Creator:
Harrison, L. J.
System:
The UNT Digital Library
Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process
Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.
Date:
December 14, 1962
Creator:
Wheeler, B. R. & Buckham, James Andrew
System:
The UNT Digital Library
High-Temperature Irradiation of UO₂-BeO Bodies
From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
Date:
January 1963
Creator:
Titus, G. W. & Saling, J. H.
System:
The UNT Digital Library
Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process
Report that summarizes the design work of the radioactive chop-leach demonstration at the Idaho Chemical Processing Plant presented in two parts.
Date:
1963
Creator:
Buckham, J. A.; P'Pool, R. S. & Pitkin, R. G.
System:
The UNT Digital Library
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date:
January 23, 1963
Creator:
Hartzfeld, H. A. & Regier, R. B.
System:
The UNT Digital Library
Safety Analysis Report : Snaptran 2/10A-1 Safety Tests
From summary: "The report contains descriptions and discussions on nuclear safety testing."
Date:
January 28, 1963
Creator:
Waage, J. M.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
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, 1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor
From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."
Date:
March 1963
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Hydrology of Waste Disposal, National Reactor Testing Station, Idaho: Annual Progress Report, 1962
Report describing investigations to determine the effect of underground disposal of liquid radioactive waste upon the regional groundwater resources.
Date:
April 1963
Creator:
unknown
System:
The UNT Digital Library