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

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 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.

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.

Last year (1948) during the flood period the flow at Grand Coulee fluctuated widely. 2 PM, June 8, 543000 c.f.s.; 4 AM, June 9, 568000 c.f s.; 2 PM, June 9, 543000 c.f.s.; 2 AM, June 10, 573000 c.f.s. A total instantaneous fluctuations of 37,500 c.f.s. was reported. Now there is installed a new control. This control can keep downstream variation within 500 c.f.s. By lowering the lake level prior to the crest period, the drum gates could be used as flood control (1948 high water basis) the drum gate control plus the water turbine discharge (if the lake level had been reduced) could have dropped the crest at Richland three feet. a. Drop in crest at Richland one foot: Electrical loss nominal, b. Drop in crest at Richland two feet: Electrical loss 1 megawatt/foot for six generators. Loss Max possible 13,310 KW each generator, 79,860 KW total (7 days). Capacity 1,170,000 KW Max Loss 6.8% for 7 days to 10 days. c. Drop in crest at Richland three feet: Electrical loss 1 megawatt/foot for 6 generators Max possible 30,100 KW each generator 180,600 KW total 8 days. Capacity 1,170,000 KW Maximum loss 15.4% for 8 to 12 days. Actual …

A preliminary report on development of filter paper for use in A.E.C. operations is presented. Filters for use in removing harmful dusts or radioactive matter from the air discharged from various operations or for other uses are described. The main fiber furnished for the paper is a specially treated wood pulp with an addition of asbestos. Filters of higher or lower efficiencies with corresponding changes in static resistance can readily be made by modifying the manufacturing formula. (J.R.D.)

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.

The 0.045 m UO/sub 2/SO/sub 4/, 0.036 m CuSO/sub 4/, 0.025 m H/sub 2/SO/ sub 4 solution (HRT fuel composition) was chemically stable during 1,866 hr of operation at 280 C and 1500 psi. The system was pressurized by boiling a 0.4 gpm stream of the fuel in a titanium heat exchanger at 313 C. During cursions were made to pressurizer temperatures above 330 C where two liquid phases were formed. These tests indicated that heavy phase began formation at 325 C (vapor pressure equilibrium temperature) as evidenced by loss of fuel from the circulating stream, Good heat transfer excluded the possibility of the missing material depositing in the form of a scale in the heat ex hanger. In each test the original fuel composition perature was lowered below 325 C. The generalized stainless steel corrosion rate during operation at 280 C and 1500 psi was 0.6 mpy for the first 700 hr and 1.6 mpy for the next 1166 hr. The average rate during the period when excursions were made into the two-phase region was 3.0 mpy. The apparent increase in corrosion rate is not easily explained because no unusual attack could be found on inspection of the stainless …

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.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Payment of fees or commissions earned in oivil proceedings in which the State is a party.

Technical report describing the process to determine the fusion welding characteristics of Haynes Alloy #25 as applied to TLJ-100530, Corrosion Loops. Hayes Stellite Alloy #25 is a cobalt-base alloy for corrosion resistant high temperature applications. This material, when welded by the inert gas shielded tungsten arc method, produces sound ductile joints. Material thicknesses greater than 12 gauge require standard joint preparations, a V joint being preferred up to 1/4 inch and a U joint for greater thicknesses. Welding heat should be kept to a minimum followed by fast cooling. The molten metal is very fluid and may present difficulties when position welding.

BS>Neutron nonelastic cross sections measurcd at different detector biases have been used to determine the cross sections for inelastically scattering 14-Mev neutrons into 9- to 14-Mev energy range. The cross section for producing these high-energy neutrons, which may be attributed to direct interaction processes, is roughly 10% of the nonelastic cross section, for all elements. A comparison is made with data of Coon and co-workers, who measured angular distributions for the samc high-energy inelastically scattered neutron group. (auth)

Abstract: "Neutron nonelastic cross sections measured at different detector biases have been used to determine the cross sections for inelastically scattering 14 Mev neutrons into 9- to 14-Mev energy range. The cross section for producing these high energy neutrons, which may be attributed to direct interaction processes, is roughly 10% of the nonelastic cross section, for all elements. A comparison is made with data of Coon and co workers, who measured angular distributions for the same high-energy inelastically scattered-neutron group."

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This is a bibliography referencing documents based on fused lithium salts within the years 1950-57.

The General Electric Company has prepared in past years numerous documents for the Atomic Energy Commission outlining in some detail its current and proposed programs at Hanford. Last year, at the request of the commission, program types of information were consolidated into one document, the HAPO Five Year Program. That document was well received and useful to an extent that the General Electric Company was requested by the Commission to prepare another covering the fiscal years 1959 through 1963. In outlining the five year program for the Hanford Atomic Products Operation, the General Electric Company has made assumptions regarding the US Atomic Energy Commission`s current and future programs and Hanford`s relationship to these programs. Two major objectives of the Commission were considered basic for future planning: first, to provide adequate atomic weapons for national defense; and second, to encourage and assist in the development of atomic energy for peaceful uses. The Hanford contributions to these objectives are conceived to include the acquisition and potential application of new technology in support of: (1) Increased production of plutonium, as nitrate solution, buttons, and as current and future shapes. (2) A program that will provide the technological capability to implement broad changes in …

Abstract: "Neutron nonelastic cross sections have been measured for 23 elements at 14 Mev, and for a selected set of these elements over the energy ranges 7 to 14 Mev and 21 to 29 Mev. Conventional sphere transmission techniques were used for the measurements. A comparison with optical model calculations of Bjorklund and Fernbach shows excellent agreement."

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.

Memorandum presenting an investigation conducted 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 of the investigation showed 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.

This report addresses the APPR critical experiment program meeting.

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The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.

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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.