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In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans (open access)

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Date: June 23, 1959
Creator: Cofield, Rogers E.
System: The UNT Digital Library
Organic Cooled Reactor Study [Part 4]: 75 Mw Power Plant Conceptual Design (open access)

Organic Cooled Reactor Study [Part 4]: 75 Mw Power Plant Conceptual Design

From introduction: This volume presents the results of a conceptual design study for an intermediate size, 75 megawatt power plant utilizing an organic moderated and cooled reactor.
Date: July 1959
Creator: Bechtel Corporation
System: The UNT Digital Library
A Brief Study of Boiling Water Reactors in the 5 to 40 eMW Range (open access)

A Brief Study of Boiling Water Reactors in the 5 to 40 eMW Range

From summary: This report summarizes the work performed in a brief study made for the AEC of boiling water reactor power plants in the 5 to 40 eMW output range.
Date: October 10, 1959
Creator: unknown
System: The UNT Digital Library
Nuclear Superheat Meeting: September 1959 (open access)

Nuclear Superheat Meeting: September 1959

From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Creator: unknown
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report (open access)

Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant (open access)

Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
System: The UNT Digital Library
Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design (open access)

Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design

From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.
Date: July 1959
Creator: Ebasco Services Incorporated
System: The UNT Digital Library
Boiling Water Reactor Study [Part 2]: Separate Studies (open access)

Boiling Water Reactor Study [Part 2]: Separate Studies

From introduction: This section presents the principal results of the optimization study done to establish the economic basis for selection of the core and fuel design.
Date: July 1959
Creator: Ebasco Services Incorporated
System: The UNT Digital Library
Boiling Water Reactor Study [Part 3]: 306 Mw Coal-Fired Installation (open access)

Boiling Water Reactor Study [Part 3]: 306 Mw Coal-Fired Installation

From introduction: The objectives of this study are to determine the estimated capital and energy costs of this typical conventional coal-fired installation, consistent with a schedule calling for completion of construction April 1964.
Date: July 1959
Creator: Ebasco Services Incorporated
System: The UNT Digital Library
Organic Cooled Reactor Study [Part 3]: Reactor Concept Evaluation (open access)

Organic Cooled Reactor Study [Part 3]: Reactor Concept Evaluation

From summary and conclusions: The purpose of this volume is to present the results of design studies to select the optimum-sized electric power station utilizing an organic cooled nuclear reactor and to evaluate and optimize the various reactor concepts, with special attention to selection of the moderator, consistent with the basic design criteria established by the AEC.
Date: July 1959
Creator: Bechtel Corporation
System: The UNT Digital Library
Report of the Fluid Fuel Reactors Task Force (open access)

Report of the Fluid Fuel Reactors Task Force

From preface: This report was prepared by a task force that met continuously in January and February of 1959 for the purposes of making a relative comparison of the fluid fuel reactor concepts for technical feasibility.
Date: February 1959
Creator: unknown
System: The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958 (open access)

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: June 24, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant (open access)

Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
System: The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T) (open access)

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
System: The UNT Digital Library
The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UOâ‚‚ Fuel Elements (open access)

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UOâ‚‚ Fuel Elements

"The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UOâ‚‚ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
System: The UNT Digital Library
Thermocouple Design and Test Program for Reactor Projects (open access)

Thermocouple Design and Test Program for Reactor Projects

Report regarding thousands of hours of testing Chromel P-Alumel thermocouple material with MgO insulation.
Date: 1959
Creator: DeLorenzo, J. T.
System: The UNT Digital Library
The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual (open access)

The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual

Report describing a computing device called the Four-Linear-Element Package Analog Computer (FLEPAC) at the Oak Ridge National Laboratory. The report includes a description of FLEPAC as well as instructions for its use.
Date: 1959
Creator: Green, F. P.
System: The UNT Digital Library
Generalized Heat Conduction Code for the IBM-704 Computer (open access)

Generalized Heat Conduction Code for the IBM-704 Computer

Report regarding a code that solves "steady-state and/or transient heat conduction problems in three-dimensional geometry" (p. 1).
Date: 1959
Creator: Fowler, T. B. & Volk, E. R.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: August-October 1958 (open access)

Homogeneous Reactor Project Quarterly Progress Report: August-October 1958

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: February 24, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1958-January 1959 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1958-January 1959

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: April 16, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: February-April 1959 (open access)

Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: August 8, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report, July 1, 1959 (open access)

Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: November 2, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Metallurgy Division Annual Progress Report, September 1, 1959 (open access)

Metallurgy Division Annual Progress Report, September 1, 1959

Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: December 16, 1959
Creator: Oak Ridge National Laboratory. Metallurgy Division.
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: October 1958 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: October 1958

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Date: 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library