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RDA-DC-3 and Program X, process tube assembly -- Design criteria (preliminary)

Description: The process tube assembly functions to provide a water-cooled channel through the reactor into which uranium slugs are inserted for processing. The channel consists of a cylindrical tube with 2 ribs towards the bottom of the inside diameter which supports the slugs in a central location. Thus providing an annular space around the slugs for the cooling water used to remove the heat generated by fission of the uranium. Because of the relative movement between the graphite and the biological shield as the result of graphite growth and thermal expansion, the portion of the process tube which extends through the biological shields at the front and rear faces must be protected against sharp bends that would prevent movement of the slugs through the tube. This requires a design which will permit such relative movement, and maintain shielding around the opening through the shield. In addition, the process tube assembly requires provisions for introducing the cooling water flow at each tube at the inlet or front face and for discharging the coolant at the outlet or rear face. Provisions are also required for opening the tube at the inlet and outlet faces to charge and discharge the slugs. This paper discusses the process tube design to meet these requirements.
Date: April 2, 1952
Creator: Nesbitt, J. F.
Partner: UNT Libraries Government Documents Department

Authorization for change in operating standards, 221 and 224 Building, pertaining to process changes during the period March 1, 1951--December 1, 1952

Description: Since the issuance of HW-17398, Separations Section Operating Standards - Part I relating to the Bismuth Phosphate Process on March 1, 1951, several changes in the process have been found desirable and have been reduced to practice. This document presents these changes.
Date: December 2, 1952
Creator: Bailor, W. C.
Partner: UNT Libraries Government Documents Department

Production Test No. 105-511-A -- Irradiation of stainless steel samples

Description: This study soughs to determine the x-ray activity of two samples of stainless steel prepared from tubing used in the ANL-140, in-pile experiment (P-13). This information is necessary in order to predict the activity of the P-13 rig at the time of removal. The primary contribution to the over-all activity will be from Ta{sup 181} and Co{sup 59} impurities.
Date: April 2, 1952
Creator: Gillard, C. W.
Partner: UNT Libraries Government Documents Department

Heat generation in stored Redox wastes

Description: Fission product activities and heat generated by fission product decay as a function of time, in waste solutions obtained by processing uranium irradiated under the present Hanford schedule, were calculated. From these data, curves showing expected heat evolution in stored Redox Process Wastes, during and following filling of the waste tanks, were prepared assuming various modes of operating the plant and various production rates. Total heat available for evaporation of water from the tanks was also determined. Under the most favorable plant operating conditions considered, calculated heat available for evaporation will be sufficient to reduce the waste volume by a factor of two. Experimental work showed that the wastes may be reduced in volume (evaporation) by a factor greater than four. Thus, supplemental heat would be required to attain the maximum volume reduction.
Date: September 2, 1952
Creator: Kane, J. S. & Burns, R. E.
Partner: UNT Libraries Government Documents Department