This report discusses studies regarding the distribution and other properties of uranyl nitrate, nitric acid, plutonium (IV) and plutonium (VI) as part of the Redox Process that separates plutonium, uranium, and fission products.

From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.

Basis: "It is desired to test the effect of neutron flux on the creep rate of zirconium. These data will greatly add to the metallurgical information needed for design specifications of reactor components utilizing this metal."

Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.

The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.

The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.

Pursuant to Dr. Kingdon's request for specific information concerning the donut pictured on pages 26-29 of WAPD-64, a close examination of this defect on Failure No. 14 was made. The slug was examined through 10 inches of Pb-glass and photographs were made. A clay impression of the surface area containing the donut was obtained, and using this impression, an Armstrong's Adhesive replica of this can wall surface area was cast.

Several failures have occurred in reduction bombs used in metal production operations. A test program is being initiated to evaluate new metals for the construction of the bomb. In the test program, a tensile specimen is cycled through temperatures simulating operating temperatures, and the time to rupture is recorded in order to estimate the life in operation of a reduction bomb made with the candidate metal. In order to find the worst stress condition, the compressive, hoop, and bending stresses must be considered.

A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.

A production test composed of preformed zirconium samples was prepared by R. S. Kemper of the Physical Metallurgy Unit⁽¹⁾ to determine the effect of exposure time and the influence of prior mechanical cold work on changes occuring [sic.] during irradiation. The first section was delivered to Radiometallurgy Unit is April, 1954, for examination after an exposure of 190 MWD/AT.

The four types of respirator cartridges used at the 202 S Building were tested against aerosols found at that location, and in the laboratory against non-radioactive gaseous ruthenium tetroxide. Positive penetration of two types of cartridges was shown with one process aerosol. Gaseous ruthenium tetroxide penetrated all types of cartridges tested. Leaks were found in some of the cartridges. Particle size of aerosol particles was measured by means of cascade impactor samples and electron photomicrographs. A high percentage of the aerosol particles was found to be less than 0.2 microns in diameter. Ru¹⁰³ + Ru¹⁰⁶ and Zr⁹⁵ + Nb⁹⁵ were shown to be present in the process aerosol by gamma ray spectrometer analysis. Possible causes of penetration of respiratory equipment by ruthenium are discussed and suggestions made for alleviating the problem.

Production Test 313-105-13-M authorized the irradiation of a uranium - 0.4 atomic per cent chromium alloy to determine the relative stability of this material during irradiation. Five tubes, each containing six four-inch alloy slugs, were irradiated to exposures ranging from 156 to 834 MWD/T. This report describes the results of the visual examination of the bare uranium alloy slugs and the results of the test to determine slug breaking strength. The breaking strength of both the U-Cr alloy slugs and the normal uranium control slugs was reduced by exposure in the pile. The breaking strength of those U-Cr alloy pieces not cracked or broken in the jackets before examination was consistently greater than the breaking strength of the normal uranium at all exposures.

In connection with the development of in-line analytical equipment for monitoring pH, gamma activity and uranium concentration in process streams, experiments and tests were carried out during the past year and a half in the Metal recovery Plant on a pH monitor for the hydrogen ion concentration in neutralized waste, a continuous gamma activity monitor on the RCU, an automatic photometer for uranium in RAF, and an automatic polarograph for uranium in RAW. This letter is written to present up-to-date diagrams of the equipment used, outline briefly the studies conducted and the main conclusions regarding design and operability of the equipment, and present material which will supplement that included in the previous reports on theses instruments.

Specifications for the proposed in-pile loop to be placed in the Hanford Reactor. The the purpose of the proposed installation of an irradiation facility accounting to a high pressure, high temperature recirculating loop for the Westinghouse Atomic Power Division (WAPD) is to test the integrity of fuel specimens. This report, in support of the feasibility study, cost estimates, and schedule, presents design specifications for the loop.

A portable, light weight transistorized alpha, beta, and gamma survey meter was designed and fabricated.

This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.

It is the purpose of this report to: 1. Present the results of a study to estimate the range of attainable boiling conditions in the 1706 KER loop design on the bases given in reference (12). 2. Present an outline of the significant modifications and equipment changes necessary to obtain the process conditions desired.

The purpose of this report is to describe the tests performed on the D-12 waste evaporator, to present and evaluate the data obtained during the test, and to make recommendations for the implementation and operation of present and future installations of bayonet tube bundles.

The purpose of this study was to develop and design a cutting torch which would slit aluminum tubes in a graphite matrix without damaging the graphite.

An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.

In reduction reactions of CeO₂, with calcium and a CaCl₂ flux, the use of vibrational energy was shown to have a marked effect on the yield of coalesced metal. Buttons of 40 to 50% theoretical yield were obtained from the vibrated reductions. As the flux concentration is decreased, the slag becomes more viscous containing undissolved CaO. The undissolved CaO present prevents the metal from completely coalescing, but the metal can be recovered from the slag and coalesced under CaCl₂ containing a small amount of calcium to reduce any oxide skin present. Cerium pellet yields of 50 to 60% metal were obtained by the procedure and were not difficult to handle in air. Cerium was used as a stand-in material for plutonium.

The purpose of this report is to establish a practical control limit for the activity density (concentration) of radioactive material that may be permitted in large-volume waste waters discharged from the Hanford separations plants to open ponds on the surface of the ground nearby, in consideration of the radiological hazards,

The design criteria are written to supply information for the preparation of a project proposal covering budget item B-2265 for Fiscal Year 1956. The function of in-line instrumentation installed shall be the rapid on-the-spot analysis of process variables for quick presentation to process operators for immediate action in process control. Alarm or safety circuits may be incorporated on the equipment.

The use of process-solution-lubricated sleeve bearings in rotating equipment is quite extensive at H.A.P.O. The difficulty or impossibility of providing contact maintenance, the poor lubricating qualities and corrosive natures of most of the process solutions, in addition to radioactivity, impose stringent restrictions on the selection of materials of construction of these bearings. Prototypical evaluation of materials indicating suitable characteristics in preliminary testing, both in the Corrosion Laboratory and in the bearing test machines, is necessary to establish behavior and compatibility under actual or simulated process conditions. These preliminary tests showed that gold and gold alloys might be used as satisfactory materials for pump bearings under certain conditions. This report presents the test results obtained while testing bearings in pumps prototypical or identical with process plant equipment.