The relative stopping powers for 300 Mev protons of H, Li, Be, C, Al, Fe, Cu, Ag, Sn, W, Pb, and U have been measured. The results are shown in Table I. The energy spent per ion-pair production in the gases H{sub 2}, He, N{sub 2}, O{sub 2}, and A at 340 Mev proton energy has also been measured. The results are shown in Table II.

This report summarizes the measurements made for radioactive contamination in the environs of the Hanford Works for the quarter April through June 1949. This belated document is issued for the records to fill in the gap for the quarterly reports not issued in 1949 because of personnel shortage at that time. Although the data summarized in this report were already reported in the H. I. Evirons Reports for the months involved, it is still of value to study the data combining the three months of data which give better opportunity to evaluate the trends and patterns of the levels of radioactive contamination emanating from the various sources at the Hanford Works. This document discusses: meteorological data and radioactive contamination in vegetation, the atmosphere, rain, Hanford wastes, the Columbia River, and in drinking water and test wells.

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Since Redox start-up, several samples of Redox PR solution have been evaporated in the laboratory as one step in a study of the Redox -- 234 coupling process. Because feed for Task I in 234-5 will be produced by evaporative concentration of Redox and purex product solutions, and because laboratory work has shown the desirability of filtering Redox solutions after such evaporation prior to use in Task I. This report summarizes the observations which have been made in the course of this work, as a guide in the design of filters for the Redox and/or Purex PR cages.

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This report discusses a system which has been conceived whereby additional flexible reactivity control in the production reactors can be achieved by introducing neutron absorbers contained in thin flexible metal strips between the slugs and the process tube wall. These splines are potentially attractive in that it is possible they could be used to provide additional flexible control during operation as well as temporary control during outages.

The effects of ``water mixing`` pieces on the axial flux distributions and reactivities of the K Reactors are discussed in this report. Two mixing piece configurations in the K piles are compared to provide a basis for determining the optimum configuration with respect to rupture control, reactivity cost and temperature cycling effects.

Studies are under ray in Chemical Research and Development to-provide the technical ``know-how`` necessary to calcine Purex 1WW and safely store the solid product. The solid product can be stored as the particulate solid from the calciner or, after further treatment, as a solid matrix or melt. In this regard, Chemical Research is studying a PO{sub 4}BO{sub 2} melt. This document presents expected fission product heat generation rates in the solid product, shows the effect of various variables on heat transfer in the stored solid, and emphasizes certain items for further study. Also a vault cooling method is suggested for further study.

The operation of a Priest Rapids dam is stated to necessitate river flow manipulation varying from 25,000 cfs to 120,000 cfs in the winter months of a critical water year. The low flow may persist for periods of six hours daily, and the expected daily average low flow is 61,000 cfs. The possible effects of this on reactor operation and waste disposal to the Columbia River which are of the interest to the Radiological Sciences Department were reviewed by J.F. Honstead, R.E. Rostenbach, and R.F. Foster. These include radiation hazards in reactor area water treatment plants, reactor area drinking water contamination; increased river temperature; chromium pollution problems; effects on downstream river usage, and effects on aquatic life.

Travel to Battelle Memorial Institute to discuss the results of subcontract research on the extended surface fuel element program and to review progress on the consolidation of Horizons` electrolytic thorium. Nickel-plated uranium samples, press-clad with 30-mil thick aluminum at 6, 10, and 15 thousand psi, have been on corrosion test for periods of 10 to 31 days. Six specimens from the 6,000 psi group have failed by undercutting after 21 to 31 days; this is another good record. Pinch welds have proved very effective as a means of sealing corrosion samples. Two 9--10 pound virgin ingots and three smaller remelts were made by consumable electrode arc melting of Horizons` electrolytic thorium. Physical and chemical data on the remelts are being obtained. Diffusion coefficients have been determined, at two sets of time-temperature conditions, for two diffusion couples of aluminum and a 0.5 w/o thorium in aluminum alloy, after high temperature annealing. The data show that the rate of interdiffusion of thorium and aluminum is very slow. These results are discussed.

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This document details radiation monitoring activities of the Reactor Section during the month of November 1954.

Recovered uranium from the Redox and TBP Plants is concentrated to 100 percent UNH by boiling off water and nitric acid in 224-U Building, and the UNH solution is then calcined or denitrated to UO{sub 3} powder in 18 batch-operated calcination pots, also in 224-U Building. Plans are proceeding now to add to the above denitration capacity by installing two additional batch calcination pots of larger diameter than the present 18 pots (6 ft. rather than 2.5 ft.). At the time of design scoping of the existing batch calcination facilities several years ago it was recognized that potential savings in direct labor and maintenance costs, and other operational advantages, would undoubtedly result from the development of a continuous calcination process. However, no continuous UNH calcination process existed at that time, and the 18 batch pots were installed modeled after similar-sized pots in use by the Mallinckrodt Chemical Company at St. Louis. A program to develop a suitable continuous UNH calcination process and equipment is now in progress with the objective augmenting or replacing the existing batch process in 224-U Building. This document sets forth the savings calculated for complete replacement of the batch pots with a new continuous process.

The examinations of seven process tubes are covered in this report. Tubas reported on are 3362-B and 0561-C. these were removed under PT-105-522-P. ``Routine Examination of Process Tubes``. Tubes 2572-C and2679-C were operating under PT-105-519-E. ``Raising Permissible Outlet Water Temperatures of Certain Tubes at C Pile``. In tube 2679-Z a rupture occurred during its operating period. These tubes (2572-C and 2679-C) were smaller diameter process tubes such as used in B, D, F, DR, and H Piles. Tube 2772-C was removed because of a suspected rupture. Tubes 3571-D and 2170-D were removed under PT-105-525-E. ``Effects of Water Quality on Pile Operation``. Visual inspection was made of the inside and outside surfaces before and after removal of the film. This work was performed in the 105-DR storage basin. Samples varying from one to four inches in length were taken from each section and transferred to the 108-B metallurgical laboratory for closer examination as regards to depth of pitting, 72-S cladding thickness, and wall thickness. The results shown in this report such as pit depth, 72-S cladding thickness and 2-S aluminum thickness are taken at specific points in each section, on what appeared to be the severest attack.

The purpose of the test described in this report is to examine the irradiation behavior of a proposed target alloy for use in Hanford reactors and to provide material for chemical separation studies.

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Progress is reported in the fabrication and inspection of metals.

The elastic differential scattering cross section of 190 MeV deuterons by protons has been measured from 15 degrees to 170 degrees in the center of mass system. The cross sections were obtained by subtracting the carbon counts from those received with a polyethylene target. Part I presents a description of the experiments. Results are shown in Table IV and Fig. 3. Part II compares these results with those expected from theory by making use of a method developed by Chew. A summary of this comparison is given in Table VII.

Since the end of the war when the long-lived isotope of carbon, C{sup 14} became available a new tool has been applied in the study of photosynthesis. Because of the interest evoked by the tracer method, research in all areas of photosynthesis has expanded. There have been reviews on various aspects of photosynthesis such as the primary photochemical reaction, quantum efficiency products, and comparative biochemistry, many discussions of which were included in the monograph of The American Society of Plant Physiologists, ''Photosynthesis in Plants''.

There are two different types of investigation of interest in high energy nuclear phenomena. One can observe gross effects such as the production of large numbers of heavy particles of different types, or one can study the elementary particles themselves which result from these collisions, for example, the kappa mesons, to determine modes of decay and the energy spectra of the resulting particles. This discussion will deal with the gross aspects of high energy interactions and will review the work of Fermi: High Energy Nuclear Interactions, Progress in Theoretical Physics, 5, No. 4, July-August, 1950.

Several of the cloud chambers used in cosmic ray research are discussed in terms of their application as measuring instruments at Bevatron energies. Some of the limitations of these instruments are revealed.

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