The Process Unit has requested the Present Canning group to evaluate two alkaline cleaners, Pennsalt A-10 and Turco ``Aviation`` Cleaner, as possible substitutes for the present trichloroethylene vapor degreaser and Duponol wash. Disadvantages of the present cleaning procedure are: ineffectiveness; expense; toxicity of trichloroethylene. The alkaline cleaners Pennsalt A-10 and Turco ``Activation`` Cleaner were tested and compared with an alkaline cleaner made from Na{sub 2}CO{sub 3} and Na{sub 3}PO{sub 4} and with the present cleaning method. With available equipment Pennsalt A-10 and Turco ``Aviation`` Cleaner did not remove grease and dirt as well as the present cleaning method. A solution of Na{sub 2}PO{sub 4} and Na{sub 2}CO{sub 3} was the best degreaser tested although it did etch the surface of the cap. This document provides a discussion of the procedure utilized and the results.

This report discusses the interim program for the production of neptunium oxide at HAPO which applies the following processing steps: isolation of neptunium from the Purex process streams, using Purex flow sheets specially adapted for this purpose; purification of the neptunium nitrate by an ion exchange process carried out in one of the Redox laboratory (222-S) multi-curie cells; and precipitation of neptunium oxalate and conversion of the oxalate to oxide in laboratory-type equipment. The process, being still in the developmental stages, is as yet subject to extreme fluctuations, both conditions and results.

This report addresses the APPR critical experiment program meeting.

The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between the two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of film, and surface area of film. A value of 1080 A was calculated as the thickness by this method. (auth)

The chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders. The effects on the critical mass of the displacement of hydrogen and the addition of poisons to the fuel were measured in water tamped and bare reactors. In this report the data obtained in the investigation is presented graphically and in tables. Some preliminary analysis has been made yielding the results: (i) the absorption cross-section of Pu{sup 240} is 925 {plus_minus} 200 barns and (ii) the minimum critical mass of Pu{sup 239} in water is 510 grams at concentration of about 33 grams per liter.

Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.

Report presenting an investigation in the 10- by 10-foot supersonic wind tunnel to evaluate the performance of a shrouded injector burner with perforated domes employed in a 28-inch ramjet using gaseous hydrogen as fuel. Steady-state data were obtained at a pressure altitude of 77,000 feet and zero angle of attack. Results indicated that burning could be initiated under severe distortion conditions and that satisfactory combustor operation was accomplished up to a pressure altitude of 110,000 feet with no adverse effect on combustion efficiency.

The final percentage of xenon created by fission in uranium and plutonium is a function of the neutron flux intensity. The flux dependence results because axenon 133 and 135 can be converted to a a stable xenon isotope by neutron capture instead of decaying into cesium.

A study of the fabrication failures for zirconium and zircaloy-2 process tubes was made. In the tube reducing operation, a non-uniform reduction in area for the cross section was found to be a major cause of failure. In annealing studies, a cycle of 2 hours at 820 deg C in vacuum followed by furnace cooling produced the greatest ductility of extruded zircaloy-2 for the annealing treatments studied. The ductility of cold worked and annealed zircaloy-2 was found to be superior to that of extruded and annealed material. The strain rate of a cold working process was found to affect the ductility of zircaloy-2.

It is proposed to test gaps corresponding to deuteron energies in the range of 0.45 to 4.5 Mev. The accelerator to be modeled is a 48 mc/sec cylindrical cavity in the TM010 mode with [formula] repeat length, [formula] gap, 0.25 megavolt per cavity foot peak r.f. gradient and strong focusing magnets alternating polarity at each drift tube.

The 0.045m UO2SO4, 0.036m CuSO4, 0.025 m H2SO4 solution (HRT fuel composition) was chemically stable during 1, 866hr of operation at 280ºC and 1500 psi. The system was pressurized by boiling a 0.4 gpm stream of the fuel in a titanium heat exchanger at 313ºC.

The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between these two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of the film, and surface area of film. A value of 1080 A was calculated as the thickness by this method.