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A Preliminary Report on the MTR Crystal Spectrometer
Report regarding the installation and testing of a neutron crystal spectrometer. This was part of a slide show presentation.
Date:
April 25, 1955
Creator:
Evans, J. E.
System:
The UNT Digital Library
The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources
Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).
Date:
April 25, 1955
Creator:
Heath, R. L. & Schroeder, F.
System:
The UNT Digital Library
Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho: Part 1 Purpose, History, and Scope of Investigations
Central subject is the ground-water geology and hydrology of the National Reactor Testing Station, with special reference to problems of water supply, water use, and waste disposal, and to the relation of these to water supply and use on the Snake River Plain.
Date:
1956
Creator:
Nace, Raymond L.
System:
The UNT Digital Library
Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho : Part 2, Geography and Geology
Geologic factors in the physical environment of the National Reactor Testing Station control the amount and availability of the water supply, the methods and efficiency of obtaining water, and the behavior of waste materials that are disposed on the ground or beneath the land surface.
Date:
1956
Creator:
Nace, R. L.; Deutsch, Morris & Voegeli, P. T.
System:
The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report
From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date:
July 1956
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO
Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date:
August 23, 1956
Creator:
Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
System:
The UNT Digital Library
MTR Technical Branch Quarterly Report, Third Quarter
Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date:
November 1, 1956
Creator:
Conner, W. P.
System:
The UNT Digital Library
Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue
Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
Date:
July 1, 1957
Creator:
Heath, R. L.
System:
The UNT Digital Library
A Neutron Absorption Alignment Chart
From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date:
July 30, 1957
Creator:
Nisle, Robert G.
System:
The UNT Digital Library
Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
Date:
September 1, 1957
Creator:
Legler, Billy Mason; Fairbourne, S. F.; Kelly, P. N. & Robinson, R. A.
System:
The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits
Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date:
September 15, 1957
Creator:
Jones, L. H.
System:
The UNT Digital Library
Chemical Processing Instrumentation and Control Research Program
Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
Date:
September 18, 1957
Creator:
Schneider, Harry
System:
The UNT Digital Library
Summary of the Spert-I, -II, and -III reactor facilities
Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date:
November 1, 1957
Creator:
Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
System:
The UNT Digital Library
Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I
Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date:
January 24, 1958
Creator:
deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
System:
The UNT Digital Library
Determination of Burnout Limits of Polyphenyl Coolants : Summary Report
Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).
Date:
February 14, 1958
Creator:
Core, T. C. & Sato, K.
System:
The UNT Digital Library
Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office
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:
March 1958
Creator:
U.S. Atomic Energy Commission. Idaho Operations Office.
System:
The UNT Digital Library
Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office
Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date:
April 1, 1958
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
System:
The UNT Digital Library
Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
System:
The UNT Digital Library
Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office
Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
Date:
April 1, 1958
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant
Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations.
Date:
August 1958
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Maintenance of ETR Coolant
Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
Date:
August 15, 1958
Creator:
Haas, F. C.
System:
The UNT Digital Library
Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide
Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date:
October 3, 1958
Creator:
Jones, L. H.
System:
The UNT Digital Library
Supplement to Standard Practices for Design of MTR and ETR Safety Circuits
Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
Date:
November 21, 1958
Creator:
Jones, L. H.
System:
The UNT Digital Library