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in subjects: "Sodium cooled reactors."  
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Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications

Description: Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date: October 9, 1964
Creator: Freede, W. J. & Roberts, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uranium Carbide Transient Heating Experiments - Phase 1

Description: Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date: August 1, 1964
Creator: Stachura, S. J.; Silberberg, M. & Cordy, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Type 304 Stainless Steel as a Substitute for Type 347

Description: Abstract: "Type 347 stainless steel was selected for SIR applications requiring resistance to corrosion in sodium on the basis of limited corrosion data and extrapolation of experience in aqueous media. Subsequent testing indicated that carbide stabilization was not necessary for good resistance to corrosion in sodium. Evaluation of the unstabilized grade of 18-8 stainless steel, Type 304, was intensified because it offered a number advantages over Type 347. Type 304 was more readily available,… more
Date: November 3, 1952
Creator: Koenig, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Eighth Quarterly Report, July-September 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, fuel testing in TREAT, fuel performance evaluation, fast-flux irradiation of fuel, and reactor dynamics and design.
Date: October 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Seventh Quarterly Report, April-June 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: July 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
open access

Effect of Eddy Diffusion on Temperatures in a Fixed Bed, Particulate-Fueled Nuclear Reactor

Description: Abstract: To assess diffusion's importance, the temperature distribution in a cylindrical reactor is derived for a coolant with uniform properties and velocity, taking into account both radial and axial diffusion, for a cosine-J0 power distribution. The fractional temperature rise of the coolant is found to be [chemical formula] where E(z) = [sin(z) + sin(Z)]/2 sin(Z), z= π x/2′, x is the axial distance from the core center, -H and ′ are the core half-height and extrapolated half-height, -H≤x≤… more
Date: November 1963
Creator: Barker, James J. & Benenati, Robert F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: April 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Power from Na Cooled Reactor : Reactor Design and Feasibility Problem

Description: The authors of this report were students in the 1951-1952 session of the Oak Ridge School of Reactor Technology. Study of a Na cooled graphite moderated nuclear reactor for power production is reported. Preliminary design calculations and results are described for a heterogeneous thermal reactor using rod type fuel elements of slightly enriched uranium. The total heat capacity is 300,000 kw with a nominal electric power producing capacity of 75,000 kw. No new experiments were made in connection… more
Date: August 20, 1952
Creator: Bennion, D. R.; Hickmott, R. L.; Krohn, N. A.; McCarthy. W. J.; Moore, R. A.; Stumpf, H. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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