A description is given of the Sodium Reactor Experiment (SRE) facilities and program of objectives. The hazards associated with equipment failures and malfunctions, personnel errors, natural causes, and operation are evaluated (C.J.G.)

With the introduction of carbon dioxide into the piles as a gas atmosphere, new problems arose which concerned the chemical reactions undergone by the pile graphite with the gas atmosphere. In the interest of obtaining a better understanding of the nature and extent of these graphite-gas reactions, mass spectrometer analyses of the pile gas from a selected sampling port at C Pile were initiated at the time of start-up of that unit and were continued until several steady state conditions had been observed. The results of these analyses are presented and discussed herein.

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In numerous instances the graphite growth in the older piles has deformed the horizontal control rod holes with a resultant jamming of the rods and overstressing of the rods and thimbles. In addition, special operating procedures to maintain very low differential pressures are required with the present allowed maximum graphite temperatures to prevent collapse of the thimbles because of loss of strength at this temperature. This is currently a limit to the power level of the H Pile. This report discusses a new rod tip and seal which have been developed to allow the removal of the thimble and permit sealing at the pile face. This will allow advantage to be taken of any future increases in maximum graphite temperature with proportional increases in allowable power.

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The results of the Hope Project, a completely rationalized reprocessing plant, are summarized. An MTR type fuel element was adopted, with U/sup 233/ replacing the U/sup 235/ and a fuel processing rate of 5.5 kg equivalent of U/sup 233/ per day. The chemical process chosen was solvent extraction, using TBP in Amsco. The Hope plant features continuous dissolving; relaxed, yet safe, criticality criteria; sampling only for process control; a realistic approach to waste storage; and a new operating-maintenance philosophy. It was felt that with the process outlined enriched fuel elements could be reprocessed for about one dollar per gram. (L.M.T.)

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This monthly document provides activities of the Radiation Monitoring group of the Reactor Section during the month of January 1954.

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Preliminary experiments indicate that there are no significant differences in the corrosion rates of zirconium or Zircaloy-2 after etching with the nitric--hydrofluoric solution or the sulfuric--nitrite solution, provided proper etching and washing techniques are followed. Incomplete removal of the residual etchant is deleterious to the corrosion resistance; however, this effect in the case of the sulfuric--nitrite solution is not as pronounced as in the case of the nitric--hydrofluoric acid solution. The anticipated advantages in the new etch were not completely realized. Additional development aimed at modifying the sulfuric--nitrite etch would have to be performed in order to overcome the disadvantages before recommendation for the adoption of the etch could be made. (auth)

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This is a progress report of the production reactors on the Hanford Reservation for the month of January 1954. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes the accomplishments and employee relations for that month.

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A meeting was held February 5, 1954 in the 2704-Z Building to discuss the ruthenium problem in the Redox Plant and to decide on a course of action to correct the problem. The following persons were in attendance.

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This document provides Part VII, Section I, Paragraphs 1 through 16 and Part VII, Section II of the Material and Equipment Section`s activities during the fabrication of reactor components and vessels at the New York Shipbuilding Corporation.