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Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)

Description: The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium sy… more
Date: April 29, 1959
Creator: Heyl, P. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Refractory Metals as Alkali Liquid Metal Containment Materials

Description: Abstract. Refractory metals and their alloys are good container materials for alkali metal coolants. Thermodynamics of interaction with contaminants have been correlated with experimental test and show the need for high purity materials. Structural metal solubility data to 1600F can be used to correlate and predict engineering systems.
Date: June 15, 1962
Creator: Cleary, Robert E., 1920-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Contamination of Cooling Water by a P-9 Plant

Description: The following sources of contamination in cooling water of the P-9 plant are considered: (1) Fission recoils, (2) Corrosion of metal, (3) Recoil from aluminum, (4) Induced activity in the water. It is found that for a P-9 plant of 3.5 x 10(4) KW contamination of the river at "X" should not exceed the .1 r criterion unless coating failure occurs. Tables of the amount of coating failure permissible are given as a function of holdup time.
Date: June 1, 1943
Creator: Friedman, Francis L. (Francis Lee), 1918-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of a Radioisotope Method to Measure Flow in the HIFAR Light Water Cooling Circuit

Description: A radioisotope method has been used to measure the flow in the light water circuit of HIFAR. A mean value of 756 pounds/sec was obtained which is in fair agreement with conventional Dall tube method. Attempts to measure the flow through individual cooling towers were not entirely successful, but some useful information was obtained.
Date: February 1962
Creator: Ellis, W. R. & Beswich, C. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development Program : Final Report on Fission Product Activity in the SM-1 Primary Coolant, Task XIII

Description: Abstract: Fission product measurements were made on the SM-1 primary coolant. The airborne activity observed during the sampling of the primary system was identified. An analysis was made on the primary coolant for alpha activity and on the secondary water for fission production iodine.
Date: June 30, 1959
Creator: Hasse, Robert A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Estimate of the Lapre Power and Steam Flow Characteristics

Description: A method of numerical solution is developed for calculating the Lapre coolant pressure drop and power output with variable coolant inlet pressure, flow rate, and reactor solution temperature. The results of a series of calculations are presented that show excessive pressure drops and sonic exit flow as the flow rate is increased and the inlet pressure is decreased. Both supercritical and subcritical coolant flow regions are investigated. Reactor power is shown to be strongly dependent on the so… more
Date: August 1954
Creator: Durham, Franklin P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Routing Upon Temperature of Cooling Stream

Description: With discussion under way concerning power production by chain reacting piles, it becomes pertinent to consider the ration of the temperature of the hottest spot in the pile to the average exit temperature of the cooling stream. This is important because the temperature of the hottest spot in the pile is one of the limiting factors in determining the maximum power at which a pile can be operated. However, the higher the temperature of the emerging cooling stream, the more efficient can be the t… more
Date: February 14, 1946
Creator: Cahn, Albert S., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Element Transient Temperature Studies

Description: A method is presented for the analysis of transient temperatures in a homogeneous circular cylindrical fuel element in a coolant channel with no axial conduction and no heat loss to the channel wall. In addition, some results were obtained for mean fuel element temperatures in power transients for a simpler model, but accounting for details of the axial coolant temperature distribution in the unsteady state. (auth).
Date: November 1, 1961
Creator: Thompson, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Purification of Carbon Dioxide for Reactor Purposes. Part III, Drying

Description: Comparison of the adsorption characteristics of the desiccants silica gel, alumina, and molecular sieves has shown that molecular sieves have by far the greatest capacity of the desiccants at the low partial pressures considered. Equilibrium data in the form of isotherms were established over the range of variables expected in the coolant circuit of a proposed Australian H.T.G.C. reactor. The mass transfer from the gas phase to molecular sieves is such that no correlation could be attempted for… more
Date: April 1962
Creator: Draycott, A. & Kerr, A. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Pebble Bed Reactor Program

Description: The coolant stream of all nuclear reactors caries some activity due to one or more of the following: a) neutron activation of coolant atoms, b) neutron activation of corrosion products carried by the coolant stream, c) fission recoil into the coolant stream, d) fission products leaking into the coolant stream. The Pebble Bed Reactor is not concerned with (1) and (b) since the helium working fluid, or coolant, has an activation cross-section which is essentially zero and its inert chemical natu… more
Date: 1960
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Flow Performance in a Multi-Loop Nuclear Reactor System

Description: The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Axial Temperature Distributions in Concentric Cooling Channels Surrounding a Heat Generating Source

Description: A set of simultaneous differential equations is established to describe the temperature distribution for coolant flow in three concentric channels separated by walls of finite thermal conductivity and surrounding a cylindrical heat source. The solution of this set of differential equations is dependent on the heat source function Q(z) which must be known or specified. An assumed function Q(z) constant is taken as being a representative case and the resultant solutions are applied to several geo… more
Date: 1962
Creator: Carr, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Fast Reactor Concepts

Description: Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date: September 1964
Creator: Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The HRT Refrigerating System

Description: The HRT refrigeration system was designed to use Freon-11 (CCI3F) as the refrigerant material in the secondary loop. A Van de Graaff irradiation of this material indicated that serious corrosion problems were probable if Freon were used in the proposed metal system. A survey was made of candidate refrigerants, and Amsco 125-82 and triethyl phosphate were selected for irradiation and physical-property determinations.
Date: January 9, 1957
Creator: Silverman, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Operation of In-Pile Loop L-4-12

Description: Loop L-4-12 was the seventh corrosion test loop operated in HB-4 beam hole at the LITR. The loop was inserted on January 24, 1956, and removed on April 17, 1956. This loop had a titanium core which was attached to the 347 stainless steel loop with special titanium to stainless steel couplings.
Date: January 7, 1957
Creator: Walter, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Secondary Refrigerant for HRT Refrigeration System

Description: The criteria for selection of an HRT secondary refrigerant system refrigerant to replace Freon-11 are given. The properties of Amsco which make it desirable are tabulated and it is compared with triethyl phosphate (the second choice) and Freon-11.
Date: January 24, 1957
Creator: Robertson, R. C. & McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test of Stainless Steel Freeze Jacket to be Used on 1/2-inch High Pressure and High Temperature Process Lines

Description: In order to test the operation of a freeze jacket in air with the process fluid closely following the conditions found in the high pressure circulation loop of a homogeneous reactor, or, 2000 psi and 300C, a test loop was built and used in conjunction with existing refrigeration equipment. The freeze jacket was made of 5/16-in. type 346 stainless steel tubing wrapped around and welded to a 1/2-in. stainless steel process line. It was concluded that for these reactor operating conditions, only a… more
Date: January 21, 1957
Creator: Draper, B. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Source of Fission Products in LITR Cooling Water

Description: A study has been made of the radioactive nuclides present in the cooling water of the Low Intensity Test Reactor. Prominent nuclides which have been identified include Np239 and certain fission products. The experimental evidence points to the probability that there could be adequate U235 contamination on the fuel plates to quantitatively account for the fission products identified in the LITR cooling water. inasmuch as new aluminum does not contain uranium, it must be assumed that the contamin… more
Date: March 26, 1957
Creator: Moeller, D. W. (Dade W.) & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Possible Radiation Damage to the Stator Windings of the HRT Circulating Pump

Description: A study of the degree and effects of radiation damage to the motor winding of the HRT 400-! canned motor circulating pumps was made. With the gamma flux estimate and the available radiation damage data, the effective life of the stator windings was estimated to be about one year, for normal operation of the pump and motor.
Date: April 80, 1957
Creator: Gift, E. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems

Description: A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date: June 5, 1957
Creator: McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cracks in HRT Flange Bolts and Ferrules

Description: When it was discovered that two HRT flange bolts of a lot of 16 spares contained serious cracks, a program was launched to (1) determine the cause for the cracking, and (2) find methods for non-destructive testing the remainder of the 672 bolts shipment, a large portion of which had been installed in the HRT. Concurrently, inspection of 8 ferrules removed from an HRT flange revealed hairline cracking in 4 of them. Magnaglo, a magnetic particle inspection method using a fluorescent dye, proved t… more
Date: January 29, 1957
Creator: Hammond, J. P.; Adamson, G. M. & Kegler, T. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fate of Fission Product Gases in the Coolant Stream

Description: The quantity and characteristics of fission products in coolant gases due to leaking fuel elements are discussed. It is concluded that the rare gases, the alkali metals, the halides, and Sb may act as permanent gases to a considerable extent. The other fission products are expected to condense out completely on walls or as dust consisting of metals, carbides, and oxides.
Date: August 4, 1959
Creator: Brewer, Leo, 1919-2005
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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