This compilation includes the following subjects: (1) Spectroscopic studies, (2) Neutral carbon in the vacuum carbon arc, (3) Anode effects, doppler blast effects, and stark broadening, (4) Neutrals in the high-current carbon arc; (5) Photon breakup of N2 in the high-current carbon arc, (6) Ion density in the high current carbon arc, and (7) Recombination cross-section for fast hydrogen ions and slow electrons. Minor revisions have been made in the subject memoranda in incorporating them in the compilation.

Tests have been completed on a combination heater-cooler unit for use in in-pile loops designed to operate in beam hole HN-1 of the ORR facility. The unit is designed to use air-water mixtures as the coolant. the coolant flows through a spiral of 3/8-inc. diameter tubing cast in aluminum around the 3/8-in. IPS loop pipe. four 1000-w calrod-type electric heating elements are cast into the aluminum, along with the cooling coils to provide loop heating.

A corrosion testing program has been initiated in Purex and Redox storage tanks to obtain corrosion data on SAE 1020 carbon steel, two alloy-high strength steels, and an alloy steel in neutralized process wastes.

This report discusses progress made by the Physical Chemistry Group and Pile Engineering Groups. Topics covered are as follows: x-ray studies--tube bore mining; physical expansion of capsule exposures; special capsule exposures; pile annealing; thermal conductivity and pile annealing; total stored energy; Sykes stored energy method; slug corrosion rate; effect of pressure drop on slug corrosion; exposure of P-10 fuel slugs; slug corrosion weight loss variables; vertical safety rod thimble corrosion; front tube corrosion; magnesium corrosion program; thimble corrosion program; horizontal thimble removal; metal exposure production tests; special pile measurements; carbon dioxide; H pile power level increase; vertical thimble temperature; graphite core samples; nine tube mock-up; and required header pressure.

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Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.

This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which they are primarily interested.

Brief summaries are given for each of the following activities for this two month period: (1) high water pressure channel (ANL-140); (2) KAPL fuel element tests (SR-79, Beta Experiment); (3) underwater facility for opening slugs; (4) strength of masonite at elevated temperatures; and (5) controlled temperature of graphite.

At about 6:30 a.m. one of the two Process Operators regularly stationed at 233-S was performing routine work in the Control Room, heard a nearby Poppy alpha detector breaking down.'' He checked and found the instrument appeared to be in operating condition as it would respond to a high level source. Further checking indicated that he was contaminated and that nearby horizontal surfaces were contaminated. This information was phoned to the Shift Supervisor who told the Operator that he would be right out and to throw a pair of shoe covers out the door. On arriving, the Supervisor donned the shoe covers and then quickly checked the Poppy response and confirmed the report of the Operator. Both men then left the building. Just outside they met the other Process Operator assigned to 233-S, returning from the lunchroom. The second Operator was handed a smear, previously taken and checked by the Supervisor, and told to check it on a Poppy in the load-out-room, a room adjacent to where the contamination was originally found. When the Supervisor heard the load-out-room Poppy break down as the smear was checked he instructed both Operators to stand by just outside the building while he went …

Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mistakes of UF4 containing from 10 to 40 w/o UO2."

Report discussing a study regarding the identification and property analysis of plutonium (IV) monobutyl phosphate, which formed as a white precipitate in another study of the effects of monobutyl phosphate on plutonium(IV) in tributyl phosphate extractions.

Introduction: "Evidence of masonite deterioration in test hole plugs was interpreted to mean that a previous estimate of the minimum lifetime of the masonite in a Hanford biological shield might be somewhat optimistic. The importance of understanding the effects of radiations on masonite for both present and future pile shields dictated that masonite be sampled from an operating pile shield and studied. The results and techniques are discussed in the following sections of this report."

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A method has been developed for the uniform coating of graphite tubes with carbides of niobium, tantalum, and zirconinm by thermal decomposition of their respective halide vapors. Conditions of coating temperature and pressure are so chosen as to prevent the deposition of metal, but to permit the formation of the carbide as rapidly as carbon can diffuse to the surface. If the carbon diffusion can be made the rate-limiting step, the coating process becomes self- regulating and uniform thickness results. The limits of the temperature-pressure range have been determined experimentally for the thermal decomposition of zirconium iodide and of the chlorides and bromides of niobium, tantalum, and zirconium. With the successful development of coating equipment and definition of conditions, 99 blowpope test specimens were coated with uniform, continuous, and adherent layers of the carbides in three ranges of thickness, light (0.001 in.), medium (0.005 in.), and heavy (0.01 in.). Determinatlons were made of the coefficient for the diffusion of carbon in zirconium carbide as a function of temperature. Exploratory work on small specimens of graphite impregnated with 7 wt.% uranium indicated that the coating results were essentially unchanged, but that loss of uranium occurred. Means of avoiding the loss of …

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The package boiler was operated at a maximum steam rate of 1750 Ib/hr at 1500 psi. The operation of the pumps, relief valves, gages, and pressure controller was checked. The time required for the boiler to come up to full operation was 15 to 20 min. On the basis of the test the boiler is considered to meet the manufacturer's specifications. (auth)

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Design data, specifications, and drawings are preserted for control rod absorber plates for the Army Package Power Reactor critical experiment. (L.T.W.)

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A coincidence circuit using the traveling wave principle as applied to distributed amplification is described. The resolving time is about 10{sup -8} sec. when the device is used in connection with scintillation detectors.

Transformation kinetics of binary U -Nb and ternary U-Nb-base alloys were investigated. Additions included zirconium, chromium, titanium, silicon, nickel, nnthenium, and vanadium. Encapsulated samples were given a homogenizstion anneal at 1000 or 1100/sup o/C, water-quenched from 906/sup o/C to retain the phase, and reheated to temperatures between 360 and 600/sup o/C. The metastability of the phase was examined by metallographic, hardness, resistometric, dilatometric and x-ray-diffraction techniques. The U -Nb system is characterized by a monotectoid decomposition of the high temperature allotrope at about 645/sup o/C to form alpha and /sub 2/, a niobium-rich cubic structure. Decomposition in U-Nb and in most U-Nb-X alloys occurred by a continuous precipithtion of alpha from the body-centered cubic phase with a resultant enrichment in niobium of until the equilibrium /sub 2/ composition was reached. In the U-Nb-Ti and U-Nb-V systems, alpha and /sub 2/ were coprecipitated. Annealing at 550 and 600/sup o/C produced decomposition products which, in most materials, originated at the grain boundaries; a fine precipitate which initiated throughout the matrix was observed at lower annealing temperatures. Increasing the niobium content resulted in greatly increased stability. The following elements added to a U-Nb base were found to retard transformation of the phase: zirconium, …