This volume is one set of a series which has been prepared as a record of the research work done under the Manhattan Project and the Atomic Energy Commission.

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The heat studies include: automatic time-delay relay for Panellit System; heating of fuel rods; installation of a thermocouple slug; effect of tube length and annulus on tube power; pressure drop film studies; full scale mock-up; flow tests; front to rear enrichment of B, D, and F piles; electrical analog studies; studies on thermal and biological shields; and recirculating system heat exchangers. Some of the topics discussed in the water studies section are: the 100-D flow laboratory; film formation test apparatus; can difference test; Calgon chemical purge for film removal; flow laboratory recirculating studies; slug jacket abrasion at high flow rates; sodium dichromate elimination tests; process water studies; and corrosion studies. The mechanical development studies sections includes the following subjects: Sphincter seal test; ball corrosion test; horizontal control rod conversion study; P-13 removal; chemical slug stripper; temperature monitoring of tube outlets; slug air weigher; slug damage; process tube replacement; crossheader improvement; water cooled test hole facility; 189-D test laboratory; creep in process tubes; charging and discharging machines; flapper nozzle assembly test; horizontal rod gland seal test; and horizontal rod mock-up test.

Topics in the heat studies section include: front and rear face reflector shields at the C-pile; process tube channel thermocouples; water temperature limits for horizontal rods; slug temperature and thermal conductivity calculations; maximum slug-end cap temperature; boiling consideration studies; scram time limit for Panellit alarm; heat transfer test; slug stresses; thermal insulation of bottom tube row at C-pile; flow tests; present pile enrichment; electric analog; and measurement of thermal contact resistance. Topics in the water studies section include: 100-D flow laboratory; process water studies; fundamental studies on film formation; coatings on tip-offs; can difference tests; slug jacket abrasion at high flow rates; corrosion studies; front tube dummy slugs; metallographic examination of tubes from H-pile; fifty-tube mock-up; induction heating facility; operational procedures and standards; vertical safety rod dropping time tests; recirculation; and power recovery. Mechanical development studies include: effect of Sphincter seal and lubricant VSR drop time; slug damage; slug bubble tester; P-13 removal; chemical slug stripper; effect of process tube rib spacing and width; ink facility installation; charging and discharging machines; process tube creep; flapper nozzle assembly test; test of single gun barrel assembly; pigtail fixture test; horizontal rod gland seal test; function test of C-pile; and intermediate test of …

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An experimental batch distillation column was used to purify UF/sub 6/ containing metal impurities. The degree of purification was determined by comparing the spectrographic analyses of the UF/sub 6/ distillate material with the original feed or pot material. Results are tabulated at 95% confidence limits. (auth)

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It is generally believed that charged particles cannot be accelerated from ground potential to ground potential unless they pass through a system which has associated iwth it a time varying magnetic field. D.C. electric fields must satisfy the equation {contour_integral} Eds = 0, while the time varying fields used in radio-frequency accelerators and betatrons are freed from this restriction of scalar potential theory. In 1932, AJ Dempster produced protons with an energy of 45 Kev, by passing them from an electrode at +22.5 kv dc to ground. The protons were first accelerated to ground potential, with an energy gain of 22.5 kev. A small fraction of the protons then picked up an electron from a residual gas molecule, and ''coasted'' to a second electrode at +22.5 kv. Then a small fraction of these neutral hydrogen atoms lost their electrons, and were accelerated to ground with a second gain in energy equal to 22.5 kev. An accelerator of this type is obviously impractical for several reasons. The probability of neutralizing a proton varies inversely with a high power of the particle velocity, so the scheme would not work at energies of interest to nuclear physicists. Even at the low energies where …

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A detailed study was undertaken to investigate the feasibility of modifying the front and rear face piping at DR and H Areas to permit increased production rates. This study is in conjunction with a larger investigation concerning methods of increasing plant production facilities. The results of the subject study indicate that approximately one year would be required for the design, procurement, and delivery of critical materials, and that the estimated construction shutdown time to complete each unit is 50 work days on a three shifts basis. Although the length of time required to perform the proposed construction work is not in line with the planned 30 day shutdown period, it is believed that the 50 days reflected by this estimate is realistic and necessary. A critical material schedule, design schedule, construction schedule and force requirement charts are presented on pages 9 to 13 inclusive.

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The 105-B Pile which was shut down on July 18, 1951 to permit removal of a ruptured uranium slug from tube No. 2169-B. The rupture was detected from effluent water monitor evidence and a survey of rear face pigtails. Removal was accomplished with the pneumatic charging machine using only normal pushing force.

Siimplified shielding calculations indicating the proposed design for the water boiler assembly will reduce the radiation at normal operaton to values well below those which are considered tolerable.

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This report describes results of an investigation to determine whether plutonium nitrates and lanthanum compounds were being entrained on the filter aid and filter block of the Nutsche Filters in Cell 2 of Bldg. 231. Leach samples were analyzed for La, Pu, phosphate, fluoride, Pu{sup 240}, and Am. From the data the authors concluded that the holdup on the Nutsche Filter is due to insoluble plutonium compounds either filtered from solution, or more likely, formed on the filter. These compounds would have a relatively low solubility in 25% nitric acid and would dissolve slowly, thus permitting a gradual buildup of material on the filter which was not detected until leaching with 60% nitric acid was instituted.

In order to change models on the RM Line, a number of equipment items must be either replaced or modified. Some items may not necessarily require replacement depending upon the severity of the change. The attached list of items will require replacement or modification before production can be shifted from the present model to any of the others previously produced at this plant. The equipment is part of the Remote Mechanical A and B lines of the Plutonium Finishing Plant.

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A considerable volume of work was accomplished during the past three months in the tracer program, experiments being conducted with At{sup 211}, carrier-free Bi{sup 206}, carrier-free Mn{sup 52}, carrier-free Mo{sup 93,99}, Np{sup 237}, Ta{sup 182} of a fair degree of specific activity, carrier-free Sc{sup 46}, and high specific activity Tm{sup 170}.

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Mechanization of the 300 Area slug canning facilities is required to obtain uniform high quality product and to eliminate variables introduced by the human element. The work to be covered by this brochure will cover requirements for mechanization of only the operations occurring within the aluminum-silicon canning bath: can and cap preheating and wetting, canning assembly, and quenching operation. Briefly, this machine will be required to insert a prepared uranium slug into an aluminum can and close the can opening with an aluminum cap. All assembly operations are to be carried out underneath a molten bath of aluminum-silicon bonding alloy. The uranium slug is preheated and prewetted before being transferred to the assembly furnace; however, the process must be so timed that proper preheating and wetting is attained before the slug is inserted. After assembly the completed canned slug is transferred to the quenching station, where the components are to be firmly held together until the molten Al-Si has frozen, forming a homogeneously bonded assembly.

The recuplex Process is proposed by the Process Assistance group of the Separations Technology Unit as a feasible method for the simultaneous and efficient recovery of waste materials in the 234--5 Building and direct coupling of the product steams from the Redox and Bismuth Phosphate Processes to the 235-5 Building operations. Demonstration of the feasibility of the process has been accomplished through the cooperative efforts of the Chemical Research, Chemical Development, and Process Assistance groups of the Separations Technology Unit and LTS described in this document.