At the time the first UO{sub 3} from so-called ``full-level`` Redox runs was shipped from 224U, the % U{sub 235} as determined in 222-S appeared high when compared with theoretical values from the burn-out curve. Close agreement between the 222-S results and % U{sub 235} determined by K-25 on lots 007, 008, and 009, however, indicated that a considerable heel of cold uranium in Redox had been blended with the first ``full level`` material. This explanation has been verified by data collected over the past weeks and provided this report. It has also been verified by the % U{sub 235} found in lots later than 010* (after most of cold uranium flushed out of Redox) which ranged from 0.66% to 0.64%.

This document provides the monthly reports for January 1952 through December 1952. These reports detail activities in the 100 areas during this time period. (FI)

This memorandum discussed review of the data from tests using alum in the treatment of pile process water, and using activated silica as a coagulant aid during period of low water temperature, which shows that this method should be substituted for the present method of treating pile process water in all 100 Areas. It was recommended that the water treatment procedures and specifications attached to this memorandum be initiated as standard practice in all 100 Areas as soon as it is possible to make the necessary equipment modifications and installations.

This report discusses seven items related to the design of the 100-K water plant facilities. These items include: the number of process water connections to the reactor building, valving at the control building, and number of main pumping units; effect on heating system of the Hanford power outage during the winter period; reactor supply conditions; power requirements and steam flow at the local power plant; the service water system; general arrangement of the heat exchanger building; and pumping station control.

Several operations that are important to the process as carried out in Task III (Reduction) are performed by the mixer. In order to specify the process certain tests were made to study these operations and are discussed in this report. They include: Mixing Time, Mixer Discharge Rate, Mixer Holdup, and Mixer Capacity. A description of the test, conclusions and recommendations is provided.

Attached is a secret draft of 300 Area expansion for the proposed ``X`` Program (600 MWD level for indefinite period) made up of the following: (1) assumptions; (2) present facilities and to what extent inadequate; (3) description of proposed work; (4) advantages to be gained and justification for proposed work; (5) why existing or alternate facilities cannot be used; (6) estimate of cost; and (7) attachments.

None

This document provides a discussion of activities at the Hanford Works during 1951.

The essential structural element which differentiates metal chelate compounds from metal coordination compounds, or metal complexes in general, is the existence of some linkage between two or more of the donor atoms in the first coordination sphere of the metal. It is the purpose of the present discussion to examine the influences that this structural factor may have upon the physical and chemical properties of chelate compounds. Examples of well known, simple coordination compounds involving a variety of donor atoms (Oxygen, nitrogen), as well as a variety of electrostatic situations are shown in the following formula. Below each one are listed a few corresponding chelate structures.

The amount of Ac/sup 227/ per curie of Ra/sup 226/ was calculated for various values of neutron flux and various Irradiation times. The amount of Th/ sup 228/ produced per curie of Ra/sup 226/ and the percentage of Ac/sup 227/ converted to Th/sup 228/ relative to the total amount of Ac/sup 227/ produced were also calculated. (W.D.M.)

The experimentally determined exponential dependence of spontaneous fission rate on Z{sup 2}/A has been used to derive an expression for the dependence of the fission activation energy on Z{sup 2}/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.

None

None

The objective of this report is to review the performance of the Redox air-filtration facilities and to present recommendations, resulting from this survey, which could improve the ventilation systems of future Separations Plants. 4 refs., 3 figs., 2 tabs.

A compilation is given of analytical procedures used in the laboratory- scale separation of radium from sulfateinsoluble residues from African pitchblende processing. Included in five alternate procedures are quantitative analyses for silica, lead, copper, molybdenum, barium, nickel, calcium, magnesium, radium, moisture, water-solubles, nitrate, silver, manganese, zinc, carbon dioxide, sulfate, and chromium. (auth)

This quarterly report details activities in analytical research by the Applied Research Unit of the Nucleonics Division during the months of April, May, and June 1952.

This report discusses the presence of corrosion products upon aluminum process tubes removed from wet portions of F Pile which led to the suspicion that the tubes might be corroding at an accelerated rate because of water entrapped in the channels between the tubes and the graphite blocks. Corrosion was especially noted on those tubes that were tightly stuck within the blocks. Analysis of the corrosion products showed that the major constituent was a hydrated aluminum oxide, containing iron oxide, calcium carbonate, and other substances in lower concentrations. This led to placement of an order for the anodizing of 200 process tubes.

The factors responsible for the advances of 100-X compared with the older areas are: Simplification of the process, such as elimination of separate process water clearwells, by having the filtered water reservoirs perform that function. Combination of separate buildings into one building, such as combining filter pump house and process pump house. Use of electric standby. Use of higher capacity pumps and filter basins, and so fewer number of units. Centralization of control and operation. More compact arrangement of plant components. Use of waste heat for space heating, recovered from reactor effluent, backed up by steam plant.

The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

None

This progress report from the Argonne National Laboratory covers the work in Biological and Medical Research, Radiological Physics, and Health services for the quarterly period ending March 31, 1952. Numerous experiments were conducted in an attempt to answer some of the questions arising from exposure to ionizing radiation, especially X radiation. Some of the research involved the radiosensitivity of cells and some involved animals. The effects of radium in humans was also evaluated. Other studies were performed in biology, such as the effect of photoperiodism on plant growth and the biological of beryllium.

None

Since the issuance of HW-17398, Separations Section Operating Standards - Part I relating to the Bismuth Phosphate Process on March 1, 1951, several changes in the process have been found desirable and have been reduced to practice. This document presents these changes.

None