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Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility (open access)

Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility

In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.
Date: June 26, 1959
Creator: Adams, O. E.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-656 (open access)

Texas Attorney General Opinion: WW-656

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Article 21.11, Texas Insurance Code, the Non-Resident Agent's Licensing Law, is applicable to persons residing in Puerto Rico.
Date: June 26, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
FATIGUE STUDIES OF INCONEL (open access)

FATIGUE STUDIES OF INCONEL

None
Date: June 26, 1959
Creator: Carlson, R.G.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report for March 1959 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report for March 1959

In a preliminary experiment, the integral diffusivity of 1 M FeCl/sub 3/ solution varied uniformly with the fraction difiused: from 0.3 x 10/sup -6/ cm/ sup 2//sec for 10 per cent diffused to 0.8 x 10/sup -6/ for 30 per cent diffused. A short Fluorox run made with crude UF/sub 4/ in the 4-in. fluidized bed showed that UF/sub 6/ could be produced from the impure feed. Denitration of Th(NO/sub 3/)/sub 4/ solutions on fluidized or mechanically agitated beds of ThO/sub 2/ and gave fine ThO/sub 2/ particles for all conditions tested. The rate of sorption of uranium into 40 micron Dowex 21K resin particles from a 0.0042 M uranyl sulfate solution was studied by measuring the uranium loading on individual beads as a function of time. Chloride concentrations of 28 to 51 ppm were produced in the solvent extraction feeds during five feed adjustment runs made with the Darex Reference flowsheet. Decladding of SS-clad /sub 4/ gave essentially identical results as batch decladding. When a Mark I prototype assembly was sheared into 0.75-in. lengths with a"plane of contact" blade in the 126-ton Manco shear, 22.2 g of metal fines (304L stainless steel) 1680 microns or less in size was …
Date: June 26, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Object Type: Report
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: April 1959 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: April 1959

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Date: June 26, 1959
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity (open access)

Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date: June 26, 1959
Creator: Jackson, P. M.
Object Type: Report
System: The UNT Digital Library
Trough-Time Dissolver (open access)

Trough-Time Dissolver

Designing a dissolver safe for up to 5 per cent U.235 enriched NPF's and having a one a ton per day capacity is a fundamental problem of Hanford NPF Program. Two basic design concepts have so far evolved, both of which employ a recirculating system in which the fuel elements are placed in the critically safe geometry separated from the bulk of the solution in another vessel. In one concept the fuel elements are charged to a set of geometrically safe cylinders or tubes and solution is circulated through them/ In the other concept the fuel elements are placed on a flat tray while solution is sprayed over them. In the latter system, nuclear safety is obtained by avoiding submerged dissolution and the resulting neutron moderation by the solution.
Date: June 26, 1959
Creator: McKee, R.W.
Object Type: Report
System: The UNT Digital Library