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Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Description: Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data o… more
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pres… more
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the r… more
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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BWR Reference Design for PL-3

Description: Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant eq… more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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PWR Preliminary Design for PL-3

Description: Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, … more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII

Description: Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."
Date: February 1, 1962
Creator: Pomeroy, D. L.
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generat… more
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors

Description: Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caus… more
Date: February 13, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator

Description: Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
Date: February 13, 1959
Creator: Pancer, Guyon P. & Zegger, John L.
Partner: UNT Libraries Government Documents Department
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Radiochemical Analysis of Crud from the Army Package Power Reactor

Description: Abstract: A study has been made of the radiochemical composition and the specific activity of insoluble corrosion products (crud) removed from the primary system of the APPR-1. This report presents the results of analysis of twelve crud samples collected during the interval from September 3, 1957 to December 1, 1957. The samples were radiochemically analyzed for long-lived gamma emitting nuclides only. Data are presented on the measured values of the specific activity of crud, the ratios of th… more
Date: February 15, 1958
Creator: Zegger, J. L.; Small, W. J. & Brown, W. S.
Partner: UNT Libraries Government Documents Department
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Summary Report of Physics Measurements on SM-1 Core I

Description: Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in th… more
Date: February 6, 1962
Creator: Weiss, S. H.
Partner: UNT Libraries Government Documents Department
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Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

Description: The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
Partner: UNT Libraries Government Documents Department
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Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant

Description: "This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
Date: February 25, 1962
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Methods, System Optimization, and Safety Studies for a 1000 MegaWatt Sodium-Cooled Fast Reactor: Task 3 and 5 report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "Evaluation of trade-off and optimization studies in which numerous design parameters and economic ground-rules are varied to determine the effect on the economics of the reference concept. Selected safety studies."
Date: February 1969
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Description: From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
Partner: UNT Libraries Government Documents Department
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Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Partner: UNT Libraries Government Documents Department
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