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This report addresses the basic research and particle accelerators.

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This report descrirs Chemical Properties of Elements 99 and 100

A description of some of the chemical properties and of the methods used in the separations of elements 99 and 100 is given. The new elements exhibit the properties expected for the tenth and eleventh actinide elements. Attempts to produce an oxidation state greater than 111 of element 99 have been successful. In normal aqueous media only the 111 state of element 100 appears to exist. The relative spacings of the elution peaks of the new elements in some separations with ion exchange resin columns are the same as the relative spacings of the homologous lanthanide elements. The results of experiments involving cation exchange resins with very concentrated hydrochloric acid eluant show that the new elements, like the earlier actinides, are more strongly complexed than the lanthanides. The new elements also exist partially as anions in concentrated hydrochloric acid, as do earlier actinide elements, and they may be partially separated from each other by means of ion exchange resins. With some eluants interesting reversals of elution positions are observed in the region Bk-Cf-99-100, indicating complex ion formation involving unusual factors.

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Boron solution circulated through special poison tubes to achieve more variable control of neutron flattening'' was tested in the 100-DR Hanford reactor. About 2700 gallons of irradiated waste Ink solution from Production Test 105-529-A was discharged to an underground crib at 100-DR, after radiochemical analyses and evaluation of radiation protection aspects by the Radiological Sciences Department. In case the Ink method is considered for production use at Hanford in the future, further biological and biophysical study is recommended to determine whether irradiated waste Ink solution may be disposed of into the Columbia River, into the ground near the river, or into the ground several miles from the river. 10 refs, 2 tabs.

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This document presents a summary of work and progress at the Hanford Engineer Works for June 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportunity to become conversant with the Purex Project. The manual may also be of assistance in orientation and training of personnel. In order to avoid repetition and duplication of effort, one line service diagrams, equipment sketches, tables, and detailed data are not a part of this manual.

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Chemistry of Feed Materials. Studies were made of the first step in the reduction of UO/sub 3/ to UO/sub 2/. The rates of reduction of pelleted- hydrated and pelleted-dehydrated UO/sub 3/ to U/sub 3/O/sub 8/ in steam were determined. The rates of reduction of pelleted U/sub 3/O/sub 8/ to UO/sub 2/ in 1-to-1 ammonia-steam were determined. Some preliminary measurements were made on the thermal conductivities of hydrated and dehydrated UO/sub 3/ wafers. Purification of Th(NO/sub 3/)/sub 4/ for spectrographic standards is described. Uranium was extracted from MgF/sub 2/ slag with an aqueous solution of sodium carbonate --bicarbonate using 0/sub 2/ at 30 psi as an oxidant. The conversion of thorium benzoate to ThCl/sub 4/ was carried out with HCl in ether. Dimethyl ether was prepared by the catalytic dehydration of methanol. The processing of UO/sub 3/ containing As contamination is described. Metallurgical Investigations. A process for stripping Af and Ni coatings from flat plates is described. Analytical Chemistry. The spectrographic determination of dysprosium and gadolinium in lanthanum oxide matrix--rare earth concentrate is described. (W.L.H.)

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The objective of the experimental studies reported herein was to demonstrate the laboratory-developed mercury-catalyzed dissolving procedure on a pilot-plant scale by conducting a series of test dissolutions of aluminum-jacketed, unirradiated uranium in the 150-gallon downdraft type semiworks dissolver in 321 Building. It was desired to establish: (1) the effect of the larger-scale operation on time cycle; (2) dissolution rates of aluminum and uranium, (3) controllability of the reactions, and (4) the concentration of mercury catalyst required.

This report provides details of a test to determine the feasibility of preventing corrosion of the 107- C retention basins by the installation of a small scale cathodic protection system.

The purpose the production test described in this document was to evaluate by pile irradiation the stability and resistance to rupture of powdered metal compacts.

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Four irradiated tensile specimens were tested in the Radiometallurgy laboratory. The uranium was from a lot rolled at Simonds Saw and STeel Company, then beta heat treated by the triple dip process. The samples were irradiated to 310 MWD/AT. The corrected exposure was 620 MWD/T after compensating for the decrease in flux depression due to the specimen size. Two of the irradiated specimens were tested in the as-received condition while the other two were vacuum annealed at 400{degree}C for 15 hours prior to testing. When the tensile properties of the unirradiated controls, irradiated, and irradiated-annealed specimens were compared, it was observed that no marked change in modulus of elasticity occurred, the 0.1 percent offset yield strength increased by a factor of about two for the irradiated and irradiated-irradiated, and 35 for the irradiated-annealed specimens, compared to the controls. The marked change in mechanical properties on irradiation as well as the relatively small effect of the anneal, indicates that the foreign atom effect caused by fission product concentration and distribution is the controlling factor, and work-hardening type of damage is relatively insignificant.

During a routine beta-gamma hand and shoe count, an employee discovered that his shoes were contaminated. This document discusses the spread of particulate contamination at the Biophysics Laboratory, Building 329, 300 Area on July 6, 1954.

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the Standard Analytical Methods manual was prepared for the purpose of consolidating and standardizing all current analytical methods and procedures used in the Reactor Section for routine chemical analyses. All procedures are established in accordance with accepted practice and the general analytical methods specified by the Engineering Department. These procedures are specifically adapted to the requirements of the water treatment process and related operations. The methods included in this manual are organized alphabetically within the following five sections which correspond to the various phases of the analytical control program in which these analyses are to be used: water analyses, essential material analyses, cotton plug analyses boiler water analyses, and miscellaneous control analyses.