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Prfr Pilot Leaching Plant-Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, the proposed location of which is in Cell B of Building 3026 at ORNL, is considered. Chemical, physical, and nuclear parameters are investigated to assure safe leaching operations. Nitric acid solvents are used for leaching the uranium and/ or thorium from the sheared spent fuel elements, and the dissolved fuel is sent through a shielded pipeline to the extraction plant for further processing. Recommended materials of construction a… more
Date: July 23, 1959
Creator: McLain, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ANALYSIS OF SELF-SHUTDOWN BEHAVIOR IN THE SPERT I REACTOR

Description: Presented at the 1958 Winter Meeting of the American Nuclear Society, December 9, 1958. Experimental and theoretical work on the selflimiting response of reactors to step and ramp insertions of reactivity is discussed along with the general characteristics of self-limiting power bursts. The static characteristics of the cores investigated are presented and the techniques of measurement are discussed. Data from step and ramp tests are presented and compared with the predictions of a theoretical … more
Date: July 23, 1959
Creator: Forbes, S. G.; Bentzen, F. L.; French, P.; Grund, J. E.; Haire, J. C.; Nyer, W. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

Description: The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energ… more
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DETERMINATION OF THE NIL-DUCTILITY-TRANSITION TEMPERATURE FOR A212B STEEL USED IN THE N.S. SAVANNAH PRESSURE VESSEL

Description: The nil-ductility-transitaion (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness locations from material used in the ipper closure head of the reactor vessel yielded NDT temperatures of 0 to 20 deg F which correspond to Charpy-V-notch impact energie… more
Date: July 23, 1959
Creator: Thurber, W.C. & Lamartine, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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