This report is a copy of a letter sent on May 23, 1944, concerning the analytical evaluation of Columbia River water by Clinton Laboratories.

This report addresses the Application of Molybdenum Surfaces to Heavy Metal.

Results of type II UF/sub 6/ centrifuge operation are presented. Data from this type operation in a single unit are useful in predicting the operation of a number of centrifuges in cascade. (J.R.D.)

On June 3 the writer was detailed to the 300 Area to study operations in Bldg, 313. Seven days were spent with C shift in the caning and dipping area. In this period, a system of coordinating press cycles was developed to utilize machine time most effectively. Subsequently, a brief amount of time was spent working in a design of the can cleaning area so as to incorporate the aluminum can etching operation and facilitate the handling and flow of materials. The next stage of perhaps a week was devoted to a study of inspection and testing methods. The final period of one week was utilized mainly to develop a method of storing finished material so as to provide the maximum amount of piece-classification flexibility without incurring enormous burdens in the movement of material to later stages of the operation.

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Transmitted herewith are three charts showing the temperatures attained at various points of the slugs in a typical tube of a flat ended pile. These charts are based on the latest information available to us on September 15, 1944. They are valid for any power load when the water rate is 21.0 gpm, whatever may be the inlet temperature of the cooling water. A simple method is provided for correcting the curves for deviations in water rate from 21 gpm. There is appended a detailed explanation of their derivation and of the evaluation of the constants involved in their construction. The current discovery that the pile will be self-poisoned by transient fission products means that the true temperature curves will be somewhat flatter than those here presented.

Information required by operators exposed to radiation hazards is discussed. All areas of the plant are subjected to radiation hazards similar to those in the radium industry. Personnel in these areas are required to wear pencil meters and special badges that are evidently not solely for identification. They are required to submit to medical examinations more stringent and frequent than usual. They are required to wear heavy gloves in one location, thin gloves in another, disposable hats or rubbers in another. They are required to stay away from familiar objects that they could handle a few days before. They observe health instrument men making readings at points not tangibly influenced by the operations. Under these circumstances, operators cannot perform their duties intelligently without being advised of the general nature of the risks involved. Since the general beta and gamma hazard occurs at nearly all points and cannot reasonably be concealed, this is the feature selected for general information. The special hazard of 105 Building can then be concealed, and the origin, but not the nature of the hazard in 231 likewise concealed.

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The bomb reaction slag produced at the ElectroMetallurgical X metal plant is at present divided into rich C-1 slag and lean C-2 slag by merely screening through a 4 mesh wire screen, the "on 4 mesh" material becomes the C-1 slag and the "thru 4 mesh" material becomes the C-2 slag. In the experiments covered by this report it was found that the concentration of the lean C-2 slag could be facilitated by the use of a 20 mesh screen for the slang separation in place of the 4 mesh screen, as the 20 mesh screen removed troublesome, small, hard lumps which passed the 4 mesh screen. Furthermore, it was found that the additional small lumps removed by the 20 mesh screen were just as rich in X metal as the larger lumps which make up the bulk of C-1 slag.

This document provides plots of expected rates of heat evolution rates of heat evolution from irradiated metal which may be useful in estimating the cooling water flow required in the the 212 buildings. A comparison of three sources of data found in the Project Handbook is provided. The CN 526 calculations agree very well with the estimates of 16, 32 and 64 days decay periods. CN 526 information was used for calculating the heat evolution rates shown in the following figures, since the data does not cover decay periods under 16 days, and does not include the 93{sup 239} contribution. The expected BTU/Min.(Ton) heat liberation rate vs. cooling time in days for through operating periods is shown. The operating level is taken as 2000 KW/Ton; the BTU/Min.(Ton) liberated may be scaled to higher or lower operating levels by arithmetic ratio. A similar curve in which the cooling water required (GPM/Ton) is substituted for BTU/Min.(Ton) is provided. The metric ton and a water temperature rise of 25{degree}C (45{degree}F) are assumed. The product content of the metal has been substituted for operating level in another plot. The rate of heat evolution is plotted against decay period for various operating times. A base …

Data acquired from the sampling of Columbia River water January 11, 1944, is presented. The water was analyzed for temperature, dissolved oxygen, and iron. The results were compared with results from samples attained from selected taps in the C.M.X. building.

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This memorandum discusses the deaeration of process water for the F area at the Hanford Engineer Works. The memorandum is dated July 13, 1944.

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Long-time tests have been made on the effect of various types of radiation on the corrosion of 2S aluminum in simulated W water. In no case was any acceleration of corrosion by the radiation observed; the effect of radiation, if any, appeared to be a protective one. Deuteron irradiation did accelerate the corrosion of mild steel at low flow rates in hot water of pH 6 to 7, but no appreciable effect was observed with copper, stainless steel, or tuballoy. The general theory of the effect of radiation on corrosion is discussed, with the conclusion that no acceleration of corrosion by radiation is to be expected in most cases of practical interest. (auth)

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Hood Worthington reports that slug testing in autoclaves shows improvement to substantiate a meeting on the initial loading of pile B and production for B.F. Babcock report examining five drafts of Operating Standards for the 100 Area. C.W.J. Wende are considering alternative loading schemes due to the observation that lead dummy slugs at the inlet end of a tube may mushroom when subjected to the stress of discharging. J.A. Wheeler reports on heavy metal content of reclaimed slugs compared to normal slugs. Also, temperature measurements on slugs in 105-B and corrosion rates of heavy metals are given. P.F. Gast reports on safety rod control calculations. T.B. Drew report on volume estimations of the B pile and analysis of data from leakage tests. Lastly, W.K. Woods reports on testing of solid aluminium dummies in the W-tube using an electric needle technique to detect motion of the pieces. Water flow considerations are discussed.

Progress on finding suitable water conditions for start-up had been approached as closely as possible with our present equipment and information as to the requirements. The water composition should be attainable that is not corrosive or build up a film rapidly, and we have means available for removal of such films. Slug classification methods were analyzed from a dimensional standpoint. Analysis of current CMX data was undertaken with the objective of establishing allowable variations in pressure drop in W-tubes due to film formation. Calculations were made of the number of slugs which have jacket temperatures in excess of various values, for various loading arrangements. On July 26 the proposed loading of the discharge nozzle is to be checked on CMX tube 1 during an inspection shut-down. Evacuation procedures in the event of a catastrophe in the 100-B area were discussed with W.E. Rapp during a visit to that area on July 19, 1944. Tests for slug leaks will not be less severe with water in the autoclave than with steam, and have a considerable chance to be more decisive, especially if a wetting agent is added to the water. Calculations were made on the sensitivity to be expected from three …

This letter was written in 1944 and applies to the amount of radiation a person could be subjected to under emergency, wartime conditions. Mr. Stone recommends to Dr. Norwood that no man should be ordered to expose himself to more than a tolerance dose (0.1r in a 24 hr period) except in the case of an extreme emergency in which time is of the essence. And that before any man is asked to exceed tolerance that a radiation trained physician be called in for consultation. His recommendations to said physician are that: (a) a single exposure of 1r would cause no harm and could be repeated at long intervals, (b) an exposure of 5 to 10r would produce loss of appetite and nausea and would increase the chances of genetic change but would cause no clinically detectable changes after the incident, (C) an exposure of 25r would do the same as (b) but with greater probability -- he would be personally willing to take a 25r exposure to accomplish an extremely important job, (4) in general keep exposures well below tolerance, (5) due to the genetic effects, women of childbearing age and younger men should be subjected to none and …

This document is a letter sent on September 6, 1944. The topic of discussion is the chemical composition of the water in the Columbia River. Tests show the amount of metals, dissolved solids, hardness and turbidity of the water before and after laboratory filtration.