A thermal analysis was carried out to determine the temperature distribution in a SNAP-8 type reactor system during atmopsheric reentry. Of particular interest are the temperature distributions in the reactor upper head, the upper grid plate, and the vessel wall. The time and altitude were determined at which the upper head falls away from the reactor core due to having a portion of its wall melted through. The time and altitude of the melting of the upper grid plate and vessel wall were also determined. The effects of reentry attitude or equivalent angle of attack and initial temperature on the thermal behavior of the system were investigated. The computer programs used in various phases of the analysis were NEWTON (drag coefficient), RESTORE (reentry trajectory), and TAP (thermal model).

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A previously reported cation exchange process for the recovery of Pu from sump water was studied in order to improve the procedure. The flowsheet calls for adjustment to 0.03M HNO/sub 3/, the addition of NH/sub 4/HSO/sub 3/ for Pu reduction, the addition of Al/sup 3 +/ to complex F/sup -/, followed by passage of the solution through a column of Dowex 50W, X-8 resin. Distribution coefficients were measured between the resin and synthetic sump solutions under a variety of possible simulated flowsheet conditions. By far the highest distribution coefficients were obtained with Pu(III) without the addition of Al. Results with Pu(IV) varied from borderline to unsatisfactory depending on conditions. It is concluded that the process will be satisfactory if the Al addition is eliminated. (JGB)

The programmed long outage which started May 1 was concluded on June 6. During this outage, the sixth heat exchanger cell was tied in, the auxiliary steam boiler was completely overhauled, four steam generators were equipped with isolation valves, extensive replacements of the process tube resistance temperature detectors were made, the reactor was re-orificed, a leaking reactor gas seal was repaired, extensive preventive maintenance was done, and numerous smaller pieces of work were accomplished. After startup, testing of the WPPSS generating station equipment was resumed. Electric power up to 320 Mw was generated, generator trip-offs were executed, and data on the reactor plant response were taken. Both the generating station and the reactor plant behaved excellently. The sixth cell installations performed as designed. Electrical power generation is now limited to about 400 Mw by the unavailability of a step down transformer on the BPA system at Vantage. Elevation of the generated power level to the rated 800 Mw will be possible in the early autumn when transformer delivery is expected by BPA. Three scrams from relatively low power levels occurred during the June 6 startup, which may be regarded as being associated with returning the plant to service after a …

Submitted herewith are source and special nuclear material composition for the month of June, 1966. Normal uranium, depleted uranium, enriched uranium, plutonium, thorium, uranium-233, deuterium, enriched lithium, neptunium-237, plutonium-238, and tritium are accounted.

This report describes the engine system (which was the first test assembly containing all major engine components to form the full-size NERVA rocket engine with an unfueled reactor assembly), the test facility and the instrumentation used in the conduct of the tests, and presents a summary of the test results.

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This report addresses the compact thermoelectric converter from April 1 to June 30, 1966.

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