BS>Some of the fundamental relationships in a nuclear rocket engine are discussed. The equations required to calculate the performance of the rocket are presented. The problems associated with these calculations are also pointed out. (auth)

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operations research, inventions, visits, and personnel status are discussed. This report is for November, 1956.

The C Reactor was proposed for producing tritium. To evaluate the performance of enriched U-Al J elements and natural Li-Al alloy target (N) elements, 60 charges containing both J and N pieces were irradiated under a variety of conditions in C Reactor. No ruptures were sustained; however Tube 3276-C was discharged because of a suspect. Corrosion rates of J elements were not worse than for natural U irradiated under same conditions. Differences between corrosion of J elements prepared by three different methods were not significant.

The November 1959 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

The November 1956 monthly report for the Chemical Processing Department of Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed was the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operations. (MB)

The radiators designated Cambridge #1 and #2 were visually examined and modified before operation. The initial examination revealed poor quality braze joints at the top and bottom plates of Cambridge #1. However, the same plates of Cambridge #2 were adequately brazed. The copper core of the fins was exposed in many of the tube-to-fin joints on both radiators, indicating that the braze material had not covered the fin collars. Samples were removed from each radiator and examined for evidence of mass transfer. Samples were also removed from the air inlet and outlet banks of both radiators and examined for fin-to-tube integrity.

In accordance with the NPR technical criteria which require that provisions be made for useful isotope production in the control rods, both isotope-producing and non-production rods have been designed. Design Analysis has been requested by Reactor Plant Design to specify the number and location of the isotope rods for the initial installation. This choice, however, cannot be made without knowledge of the fuel element characteristics and a prediction of the reactor operating techniques. Some of the factors affecting the use of isotope-producing rods are discussed in this letter, and the following recommendation is made.

This is a progress report of the production reactors on the Hanford Reservation for the month of November 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

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The corrosion rates of slug jackets exposed in the Hanford piles are monitored to determine optimum operating conditions and to evaluate proposed changes in process specifications. Selected process tubes are charged with weighed slugs, and the coolant flow rate and temperature rise through the tubes are recorded until the slugs are discharged. The corrosion rates of these control slugs are computed from weight loss data after discharge. The data obtained in this manner are used to find the relationship between slug jacket corrosion rates and the various conditions of power and temperature that are encountered in the piles. This report covers all of the corrosion data obtained to date for slugs that have been cooled with the currently specified process water, which is alum-coagulated and contains 2 ppm sodium dichromate as an inhibitor (see Appendix II for the water composition). All of the slugs were normal production pieces canned in 2-S aluminum.

It is believed that the overall safety of reactor operation will be improved upon completion of projects CG-558, 600, even at the higher power levels anticipated. Installation of sub-critical monitoring instruments concurrent with these projects is a factor in this conclusion. Higher power levels will not of themselves increase the probability of a disaster initiating event; however, higher power levels will reduce the time available for remedial action and will increase the severity of the consequences of a disaster. Loss of process cooling water will precede or accompany a reactor disaster. A reactor containing a normal inventory of fission products will surely be destroyed, with release of some fission products, if cooling water is lost at operational power levels or within hours after shutting down the reactor from operational levels. A power excursion along with the water loss, unless causing a puff release of fission product, will only hasten the destruction. A power excursion not caused by loss of cooling water is possible, but appears to be of almost negligibly small probability. Such an excursion will not become disastrous unless a significant fraction of the cooling water is boiled out of the reactor. The scope of projects CG-558 and CG-600, …