Regarding heat transfer studies of annular spaces around the process tube, there is general agreement among all concerned, that high graphite temperatures are essential at the initial startup. Pile Technology, in studying graphite damage, has developed information that shows little or no expansion occurring when temperatures are maintained at 275{degrees}C. Stored energy levels are less than 5% and K/Ko has saturated in the region of 3.5 to 4. Badly expanded samples (1% increase in length) have recovered 75%. This, of course, is in the pile, since nonlinear annealing is necessary, temperature alone not being sufficient. You may refer to HW-14522, HW-14310 and HW-13117 for further discussion of these points. Based on this assumption we should select some minimum startup temperature, for the edge of the active zone, say 200{degrees}C as a starting point.

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It is recommended that the actual intensity existing today above the liquid be measured before recommendations are made on cutting through the concrete seal. A detailed statement of work on this problem follows. The calculations have been filed. In the study of the feasibility of cutting through the concrete seal on the center riser of the waste storage tank the radiation intensity that would be encountered is critical because director operator contact would be required. The question of the radiation intensity to be expected was approached from two standpoints: (a) a study of previous measurements of sludge level and activities in the storage tanks; and (b) direct calculation.

Progress is reported by the Mechanical Development group and by the Plant Assistance group. The Mechanical Development group reports on the thimble removal program, special pile measurements and instruments, graphite sampling, and the ruptured slug problem. The Plant Assistance group reports on technical information on the B, D, F, and H piles, special request container slug, exposure of P-10 fuel slugs, slug corrosion studies, front tube corrosion, and flow laboratory experiments.

This document is the progress report for the design and development of Pile Area {open_quotes}G{close_quotes}, to cover the period June 1, 1949 to December 31, 1949. This project represents the major effort of the Reactor Division of the Design and Construction Divisions. It is being pursued with the aim of being able to incorporate the major project objectives in a finished pile design if that design is begun about January, 1951.

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This document discusses a meeting held to inform members of the Biology Division of the status of P-10 problems, to exchange ideas on methods of attacking these problems, and to consider new problems.

This document provides a discussion of the design features for the P-10X Project needed in Building 109-B.

This is a progress report of the production reactors on the Hanford Reservation for the month of May 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This is a progress report of the production reactors on the Hanford Reservation for the month of June 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Brief summaries are given for each of the following activities for this two month period: (1) high water pressure channel (ANL-140); (2) KAPL fuel element tests (SR-79, Beta Experiment); (3) underwater facility for opening slugs; (4) strength of masonite at elevated temperatures; and (5) controlled temperature of graphite.

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This is a progress report of the production reactors on the Hanford Reservation for the month of November 1950. This report takes each division (e.g. manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This is a progress report of the production reactors on the Hanford Reservation for the month of October 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This memorandum concerns the relative activities of Argon 41 and Nitrogen 16 in the pile gas composed of 95 percent carbon dioxide and 5 percent air. The memorandum is dated November 16, 1950. (JL)

The present liquid third safety is considered undesirable for the piles at their present power levels. Any increase in power level and graphite temperature makes the need for an alternative third safety increasingly imperative. The use of the third safety is envisioned under conditions where the supply of cooling water to an operating pile is interrupted and concurrently the safety rods full to enter the pile because of slight shifting of the top shield or larger shifting of the winches, relative to the pile proper. Under these conditions, undesirable properties of a liquid third safety are present and are discussed in this memorandum.

Though the product of P-10 is T{sub 2}, the chief hazard is the tritium oxides, and tritium in water vapor might exchange with the hdyrogen in the water. If a catalyst is present, essentially all of the tritium would be exchanged. Because we do not know what catalyzers may exist at P-10 or in the lungs of a person breathing tritium, a ready answer cannot be given to the question of the importance of the exchange reactions. The HT + H{sub 2}O {r_reversible} HTO + H{sub 2} is also considered. The same conclusion holds, most of the tritium will be exchanged; however the equilibrium constant is needed. 1 fig.

A method has been adapted from ion exchange studies for removal of the fission products, Cs-137, Sr-90, and the rare earths for both untreated urine samples and the supernates from the precipitation steps in the TTA procedure for plutonium. Because of the excessive amount of eluant necessary to separate the fission products and the resulting time required to run a separation, a method was developed to remove the Sr-Y, Ce and Pr by chemical means and Cs from the raffinate of this extraction by ion exchange. It should be noted that Cs is easily separated from Pu in the separations plant, and that is presence as a contaminate in the outer areas is not as probable as the other long-lived fission products. This fact has been born out in three years of analyzing contaminated samples from the 200 Area by the H.I. Development Divisions.

In November, 1949, an industrial hygiene study was made of the operations conducted in the Bio-Assay Laboratory, 706 Building, 700 Area. This study was conducted by W.E. Gill and reported in HW-15654. One of the potential health hazards investigated was the use of benzol in laboratory procedures. An evaluation of this problem where the solvent was employed for cleaning glassware indicated that the solvent vapor was present in the workers` breathing zone in concentrations occasionally as high as 170 ppM. Five samples collected at this washing operation showed an average concentration of over 100 ppM; all samples being over the maximum allowable concentration (MAC) of 35 ppM. As a result of the findings of this study several recommendations were made, one of which was the advisability of instituting a program for urine sulfate determinations for the laboratory personnel exposed to benzol. It was felt that this test would demonstrate more precisely than air sampling the actual inhalation and absorption of solvent vapors experienced by the operators and exemplifying such factors as variations in individual respiratory rates and care in the use of solvent during washing.

This HAPO report documents the design criteria for the P-10 air monitor at the 300 Area. Minimum reliable readings and accompanying remarks document testing of four different monitors.

As the result of repeated over tolerance monitoring samples taken by H.I. Survey in Room 7 of 2228 Bldg., 200 East Area, an Industrial Hygiene study of the air contamination in this room has been made at the request of the H.I. Area Supervisor. Observations made during the preliminary survey and throughout the study indicate that the ventilation system together with the decontamination operations; slurping operation, Goldberg operation, and certain activities during bench determination of process examples, are the major contributors to contamination in the room. While it is felt that the major sources of contamination have been pointed out, there are many specific operations that have not been studies. Recommendations include: Replace the air supply grills with air diffusers, so that air will be supplied to the laboratory without drafts; Provide hoods over the decontamination sinks large enough to accommodate all manipulations involved in decontamination procedures and with sufficient exhaust ventilation that will maintain a minimum face velocity of 200fpm; Provide a hood over the slurper, larger enough to accommodate all manipulations, and ventilation to maintain a minimum of 200fpm at the hood face and any other openings; Provide an enclosure over the Goldberg such that positive exhaust ventilation …

This report consists of an outline for a program for testing the air-supplied face masks currently being used as protection against P-10 atmospheres at HAPO. The test procedures which follow are intended to determine circumstances under which the mask ceases to offer protection to the wearer. To keep the scope of the test program to a minimum and also to facilitate interpretation of the findings in the light of P-10 atmospheres, the test conditions chosen were those which would be most unfavorable for the mask from a protection standpoint.

Paper describes procedures used at Hanford to bioassay plutonium in urine samples.