Report issued by the Office of Saline Water over studies conducted on the reverse-osmosis program. The methods of desalination through osmosis are discussed. This report includes tables, illustrations, and photographs.

The original test authorized the discharge of three columns of irradiated fuel elements from KE Reactor as a first step in an Operational Recharging program. Purpose of this supplement is to authorize discharge of any number of columns of irradiated fuel elements after shutdown, and to continue in force Supplement A, with changed timing of operational discharge.

The Overbore Test Facilities of the C Reactor are to be expanded to permit pilot testing for the complete conversion of the reactor to enlarged fuel channels. This report sets forth the technical bases and appropriate criteria to accomplish this work.

This report, for April 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Financial operations; facilities engineering; research; and employee relations. Weapons manufacturing operation; and safety and security.

The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New parameters are derived in this document for future total control calculations.

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Declassified 21 Sep 1973. A wide range of metallic hydrides (to NH 9.0), each containing additives to tailor the nuclear characteristics, have been fabricated successfully. Specific additives have included B compounds and high Z- material compounds, e.g., W, Hf, Th. Hydrided Ti which contains B compounds has proven relatively easy to fabricate and has shown excellent radiation stability. Post-irradiation appearance (through 6 x 10/sup 20/ nvt thermal) shows no visible changes. Strengths to 150,000 psi at 380 deg C (with ductile failure) have been observed for TiH. Sound, massive N/sub H/ 6.9 hydrided Zr rods have been fabricated in hydride-furnace batches as large as 50 kg, with 100% yield. A 50 Th-50 Zr hydride of N/sub H/ 6.7 and higher has been fabricated. The basic structure, apparently ThZr/sub 2/H/sub 8/, is a cubic spinel-type structure and is the first reported hydride having this structure. This material, when containing a B compound additive, will probably provide more gamma shielding than is generally needed, but the material has interesting possibilities as a combination breeder-blanket-shield. It now appears that almost any combination of looked-for nuclear properties can be incorporated into a metallic hydride composite having useful engineering characteristics. (16 tables, 23 figs) (DLC)

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A calculation of tritium beta energy absorption in spherical bulbs filled with mixtures of tritium and other gases is ' carried out under the empirically substantiated assumption that the energy absorption per spherical shell surrounding a point tritium source is representable by a pure exponential function. Primary and successive backscattering at the wall of the vessel is taken into account by means of a very approximate calculation. The computed energy absorption function for hydrogen gas in a silvered bulb agrees within plus or minus 3% over a wide range of gas pressure with the one available set of spherical ionization chamber data. (auth)

Pu nitrate production was above revised forecast. 141 kCi Sr-90 was isolated in Purex and stored for decay; to date, 1190 kCi has been recovered from Purex wastes. Casks of Cs-137 and Sr-90 were turned over to AEC for ORNL. Production of UO{sub 3}, Pu metal buttons, and weapon component fabrication exceeded forecasts. Purex processing continued until April 14. The Purex neptunium campaign had low yield because of loss to waste system. The cartridge in the Purex co-decontamination column scrub section was replaced with a new design. After the Redox organic distillation pot was replaced, {gamma} activity in Redox recovered hexone increased 300 {times}; product quality returned to normal after the faulty steam traps were replaced. Fabricated parts underwent dimensional changes after machining and gaging; part dimensions have been altered to compensate. Design for the proposed caisson-lateral leak detection system was revised to contain 3 horizontal laterals beneath each tank and 7 vertical wells around each tank. A ratio exists between the Cs-137 in the coating waste solution and the total U in liquid and precipitate phases. (DLC)

The effect of isolation and forced draining on the radiation level of the 1AC coolant purification hairpin loop was investigated. The activity in the horizontal and vertical legs (U-bend) of the loop piping was determined by a radiochemical analysis of the crud deposits. (C.J.G.)

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The objective is to establish, from test results, the relationship between pressure loss and orifice configuration, mass rate, and steam quality, for a Fuel Cycle fuel assembly.

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