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in publisher: "Mallinckrodt Chemical Works Saint Louis, Mo."  
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Structural Testing of SM-2 Fuel Elements

Description: Ability of the originally designed SM-2 stainless steel fuel elements to withstand static transverse pressure gradients of normal reactor operetion was investigated. Fourteen simulated original SM-2 type fuel elements by Tungsten inert gas (TIG) and electric resistance welding processes were subjected to pressure gradients to 6 psi and measured for deflection during stress and distortion after stress. Tests provided a basis for selecting a reference SM-2 fuel-element design and established a me… more
Date: September 29, 1960
Creator: Coleman, F.G. Jr. & Herbert, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SUMMARY OF REACTOR DESIGN INFORMATION FROM THREE YEARS' OPERATION OF A SMALL PWR

Description: Reactor design information obtained from 3 years' operation of a small pressurized-water reactor, the SM-1 (formerly APPR-l), is presented and discussed. The SM-1 reactor, designed to produce 10 Mw(t) power, employs fully enriched uranium fuel in the form of UO/sub 2/ dispersed in stainless-steel fuel plates. The reactor is cooled by water at 1200 psia and mean temperature of 44) deg F. Core-physics measurements were performed of temperature coefficient, pressure coefficient, rod calibration, s… more
Date: September 1, 1960
Creator: Gallagher, J.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

Description: The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifica… more
Date: September 14, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-1--RESEARCH AND DEVELOPMENT QUARTERLY REPORT FOR APRIL 1 TO JUNE 30, 1960

Description: With the exception of a brief period of slightly elevated chloride level in the secondary blowdown, water-chemistry conditions during the period were satisfactory. During the period, the reactor was shut down for end-of-core-life testing and rearrangement. A set of specifications covering all electronic and electromechanical mechanisms required to control the SM-1 reactor through the rod- drive motors and clutches was prepared and issued. Installation of instrumentation for plant response and s… more
Date: September 20, 1960
Creator: Bergman, C. A.; Brown, W. S. & Hasse, R. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-2 Task 3 Mechanical Design Report for October 1958 to March 1960

Description: Progress on design studies under Task 3, the mechanical-design portion of the SM-2 core and vessel design, is summarized for the period Oct. 1955 to Mar. 1960. Task 3 covers the mechanical design of the reactor vessel, vessel closure, nozzle penetrations, steel reflector, core support structure, flow divider, control rods, absorbers, and fuel elements. Layouts showing the basic designs, major dimensions, and materials of construction are presented. Stresses for the reactor vessel selected were … more
Date: September 20, 1960
Creator: Connolly, T.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Final Report for January 1, 1959 to July 1, 1960

Description: To determine the thermal stability of SM-2-welded plate type fuel elements, test specimens were subjected to temperature differences across plate width. Thermal deflections caused by the relatively cool side plates restraining the axial expansion of the fuel region were measured along the axial centerline of the test specimens. Region-averaged temperature differences varied from 0 to ll6/sup o/F, or about l35% of expected reactor operating differentials. Test specimens, machined from standard f… more
Date: September 20, 1960
Creator: Christenson, J. A. & Kortheuer, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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