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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F

Description: Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date: February 28, 1961
Creator: McDonald, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Theory of Hyperfragments

Description: "Mesic decay of hyperfragments is discussed systematically on the basis of a previous model for hyperfragments. The general formalism for the two-body and three-body mesic decay was developed. The polarization-direction correlation and the angular correlation for the two-body and the three-body decays are discussed together with the decay probability. The formalism was developed so as to include the isotopic spin selection rule ( DELTA I = 1/2 and 3/2) for the mesic decays. The theory was appli… more
Date: February 28, 1961
Creator: Iwao, Syurei
Item Type: Refine your search to only Report
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)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface Motion from an Underground Detonation

Description: Abstract: Surface and near-surface acceleration and strain were measured on a deep underground nuclear burst (Rainier Shot; 900 ft; 1.7 kt) to permit extrapolation of results to nuclear detonations of other yields under different test or employment conditions.
Date: February 28, 1958
Creator: Swift, L. M.; Sachs, D. C.; Brenner, J. L. & Wells, W. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Water Hammer Tests Loop Able Pwp Land Reactor, 1957

Description: "This report essentially substantiates the preliminary data reported ln WAPD-PWR-PMF-898. The Primary Coolant System of the Pressurized Water Reactor (PWR) at Shippingport, Pennsylvania, comprises four loops. Each of the loops has one pump to control the mass rate of water flow-. A series of tests were conducted on the cooling system of the PWR land reactor to determine the magnitude and duration of the water hammer pressure wave resulting from check valve closure. The water hammer pressure wav… more
Date: February 28, 1958
Creator: Brewer, G. A. & Wing, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Digestion and Filtration of Leached Zone in Pilot Plant

Description: Introduction: The present report summarizes pilot plant operations on the sulfuric acid digestion of -200 mesh leached zone and filtration of the digested slurry for the period May 5, 1952 through August 7, 1953.
Date: February 28, 1955
Creator: Dugger, Gordon L.; Adams, J. B. & Bart, Roger
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Rapid Sensitive Direct Method for the Routine Determination of Radium in Urine and Other Biological Materials

Description: Report discussing a method for determining the amount of radium that may have accumulated in the body of an individual by the direct counting of alpha particles from radium in biological materials such as urine.
Date: February 28, 1950
Creator: Russell, Edwin R.; Lesko, Roman C. & Schubert, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Heavy-Water Homogeneous Pile: a Review of Chemical Researches and Problems

Description: Technical Report: A generalized review of the chemical problems and researches related principally to the heavy water homogeneous pile is presented herewith. The report covers researches performed principally by the Columbia Group who initiated the study. This report contains a chronological outline of the development, a discussion of some special topics whose significance is paramount in any slurry pile discussion, and finally an outline of important research problems remaining, roughly grad… more
Date: February 28, 1944
Creator: Hiskey, C. F. & Eidinoff, Maxwell Leigh, 1915-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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