Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)

Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)

ON NUCLEAR PHYSICS LABORATORY AT CANEL. The critical experiment facility at CANEL is described. Information of the mature of experimental assemblies and operations is included. Safety features of the building, equipment, and operations are pointed out. Possible accidents and the resulting hazards to surrounding areas are analyzed. The make-up of the surrounding area is described. (M.C.G.)

for filtration of plutonium oxalate slurries. A scalpel produces a slit in the filter precoat, leading to increased filtration in this slit, and the oxalate is removed by a doctor knife; this technique results in prolonged blowback cycles and more uniform delivery of filtered oxalate to subsequent processing steps. Several types of filter media were tested, and rigid porous aluminum oxide was found to be the best one. (D.L.C.)

Activities during the period were directed primarily toward determination of the engineering properties of hydrided materials. The tensile strength and elongation, thermal expansion, thermal conductivity, and heat capacity of ZrH were determined as functions of temperature and H content. Preliminary results of Ti-base material studies indicate that these materials can be used for shielding and structural materials with the incorporation of rare earth hydrides. A summary of the work from Oct. l958 to Sept. 1959 is included. (J.R.D.)

Whence came life on the surface of the earth? Whether or not a complete answer to this question may be found within the context, and content, of modern science, may be a moot question. It is our purpose to see how far we can devise an answer, and how satisfactory it may be, within that context. We trace a path from the primitive molecules of the primeval earth's atmosphere condensed from space through the random formation of more or less complex organic molecules, using the available energy sources of ultraviolet light, ionizing radiation or atmospheric electrical discharge, through the selective formation of complex organic molecules via autocatalysis, finally, to the informatiion-transmitting molecule which is capable of self-reproduction and variation. In addition, somewhere, either during the course of this Chemical Evolution, or perhaps succeeding it, a system has been evolved in which the concentration of the reaction materials was retained in a relatively small volume of space, leading to the formation of cellular structures. Man is about to send back into space some bits of the dust from whence it originally came, It is thus not only timely but more significant than ever before to ask again the question: What are …

The operational characteristics of the Cosmotron were reviewed in brief. Since a rather complete account of this machine is now available in the September 1953 issue of Rev. Sci. Inst., this summary will include only the more recent utilization of the machine as a research instrument.

Project CG-588 authorized the design and construction of dissolver and waste neutralizer off-gas scrubbers to remove the ammonia given off during coating removal and waste neutralization steps of the Redox operation. It has always been recognized that the nitrogen oxides in the dissolver off-gases, resulting from the dissolution of bare uranium slugs, could also be absorbed in water under proper conditions to give re-useable nitric acid. Consequently it appeared feasible to provide facilities which would combine these ammonia removal and nitric acid recovery operations. The purpose of this report is to present a scope design for the economical recovery of nitric acid from the Redox dissolver off-gases in addition to the removal of ammonia. It is recognized that acceptance of this scope for project execution would make unnecessary the ammonia scrubbers for the dissolver off-gases of Project CG-588. 8 refs.

None

None

It is considered appropriate occasionally to make independent checks on the effectiveness of the plant laundry in removing radioactive contamination from plant-issue protective clothing. Previous surveys have offered constructive criticism resulting in improved handling of high level and soft beta contaminated clothing and incorporation in new designs of ventilating and air sampling recommendations. Recurrently the adequacy of laundry reject limits is questioned, and only recently an accurate, special study resulted in relaxed limits for Metal Preparation area clothing. A current question concerns the advisability of determining the reject level on the beta-gamma monitor more frequently than once a day. 2 tabs.

None

None

This report has been prepared in answer to the request from the AEC contained in the letter of October 1, 1957, from A. T. Gifford, HOO to A. B. Greninger. As requested, the report is of a summary nature and a more complete discussion of many of the points considered will be found in the references listed. The report is directed primarily at C reactor but some discussion of the other reactors is also included. A description of the proposed utilization of I E slugs in C reactor together with the associated power increase schedule is presented below. The reasons for changing to the I E element are presented together with a comparison of solid and I E slugs in the C reactor. The changes being made in C reactor under CG 600 are described. The operational characteristics of the C reactor using solid and I E elements are compared and finally the nuclear safety status of all of the Hanford reactors assuming I E loadings is reviewed.

None

None

None

The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error, if any, that is induced in a standard Vernatherm unit of known calibration when subjected to gamma irradiation. The accuracy of the units prior to irradiation was within 1.25 F. An examination of the calibration curves shows that a hysteresis effect in the hydrocarbon of the unit causes the curve of descending temperature to be displaced from the ascending temperature curve. The effects of irradiation were to decrease the accuracy to within 3.75 F. After a total exposure of 17,416 {times} 10{sup 4}R at 1.1 MEV. Since the exposure of 11,441 {times} 10{sup 4}R is equivalent to approximately 2,000 months exposure in the pile at 250 MW they can conclude that the effect of radiation is not detrimental since the increase in …

The purpose of this document is to present the bases and calculations which resulted in the conclusion given in the letter of October 17. Also, the original calculations were made on the basis that the webbing face thickness is equal to 1/2 inch, which is no longer the case. The new thickness is 3/4 inch. This alters the condition of heat generation. Consideration is given to the heat generation in the legs.

From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is possible by scavenging these wastes. In this document, a chemical flowsheet is presented for use as a design basis of facilities which will permit scavenging of these stored wastes.

Many factors are responsible for the rapid growth of analytical chemistry during the past ten to fifteen years (This report was written in 1953). One of the most important of these factors is the greatly increased significance to present day chemistry of many elements that in the recent past were principally chemical curiosities. Since the Atomic Energy program is concerned with many such elements, it is of interest to discuss the cause for this concern and the resulting effect on the field of analytical chemistry. A number of pertinent analytical research problems at Hanford are cited as examples.

In order to carry out the program of increased pile operating levels either tube outlet temperature or the water flows must be increased. This program proposes a considerable increase in both the pile effluent water flow and temperature. Consequently an investigation was started of problems that might be encountered in the pile effluent system. Later, a decision was made that the portion of this investigation dealing with the effects of increased water flow would be handled by the Pile Materials Unit. Therefore this report serves to present the results of a preliminary investigation of the effects of increased water flow and temperatures.

This is the monthly report for the Hanford Laboratories Operation, September, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This report describes the operation of the fuels preparation department for the month of September, 1957. Manufacturing employee relations, process development, plant improvements and financial operations are described.