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A Transistorized Pulse Height Analyzer for Gamma Spectroscopy

Description: From abstract: "A scintillation detector has a pulse height output which is a linear function of the energy of impinging gamma radiation. A pulse height analyzer system determines the amplitude distribution of this train of pulses. The system also displays this information graphically in a form which is convenient for further analysis."
Date: March 23, 1959
Creator: Graveson, R. T.
Partner: UNT Libraries Government Documents Department

Sodium Components Test Facility

Description: Development of more reliable, lower cost components for high temperature liquid metal-cooled reactor plants.
Date: November 1959
Partner: UNT Libraries Government Documents Department

Specifications and Fabrication Procedures for APPR-1 Core II Stationary Fuel Elements

Description: Report regarding the design requirements and manufacturing procedures for the stationary fuel component proposed for operation in the second core loading of the Army Package Power Reactor at Fort Belvoir, Virginia.
Date: 1959
Creator: Cunningham, J. E.; Beaver, R. J.; Robertson, R. D. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department

Instrumentation and Controls Division Annual Progress Report, July 1, 1958

Description: 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.
Partner: UNT Libraries Government Documents Department

Generalized Heat Conduction Code for the IBM-704 Computer

Description: 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.
Partner: UNT Libraries Government Documents Department

Plutonium Recycle Test Reactor Final Safeguards Analysis

Description: Report describing the Hanford Plutonium Recycle Test Reactor (PRTR), its building, safety procedures, site, operations, and analyses of its safety features.
Date: October 1, 1959
Creator: Wittenbrock, N. G.; Walkup, P. C. & Anderson, J. K.
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Partner: UNT Libraries Government Documents Department

Radioactive Waste Management at Oak Ridge National Laboratory

Description: Report documenting "[t]he collection, treatment, disposal, and monitoring of radioactive wastes (solid, liquid, and gaseous) at Oak Ridge National Laboratory" (p. 2).
Date: 1959
Creator: Browder, F. N.
Partner: UNT Libraries Government Documents Department

Physics Division Annual Progress Report, March 10, 1959

Description: Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.
Date: June 10, 1959
Creator: Oak Ridge National Laboratory. Physics Division.
Partner: UNT Libraries Government Documents Department

Description of Purex Plant Process

Description: Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date: May 19, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "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-UO₂ 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.
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Partner: UNT Libraries Government Documents Department