None

The GE Nucleonics Division Staff Department which now is called the Radiological Sciences Department was formerly known as the ``Health Instrument Divisions. A part of this department, presently known as the Biology Section, was formerly identified as the ``Biology Division.`` This project is concerned with a laboratory facility which is being built for the use of the Aquatic Biology Unit of the Biology Section. The Aquatic Biology group was established in 1945 to study the effect of the pile effluent on the Columbia River salmon industry. A hutment was erected to provide space for a laboratory, fish troughs, equipment, offices, and service. Thirteen outside ponds were built. Although minor improvements were subsequently added to the original facility, the expansion of the plant did not keep pace with the expansion in the operating program. This inadequacy gave rise to the project hereafter described.

A number of alloys of zirconium have been investigated as part of a program aimed at improving the high-temperature tensile and creep strength of zirconium. These alloys include aluminum, beryllium, lead, magnesium, molybdenum, niobium, tantalum, tin, titanium, tungsten, vanadium, and zinc, binary and ternary alloys.

None

None

Report presenting a hematological view of clinical data related to acute and subacute radiation injuries caused by atomic bomb detonations in Hiroshima (August 6, 1945) and Nagasaki City (August 9, 1945), Japan. It includes data and observations of more than 4,000 case records collected between September 1945 and October 1947.

None

None

Previous computations of cross sections for the D-D and D-T reactions were dependent on the knowledge of the energy loss of deuterons and tritons in D{sub 2}O ice targets. Recent Published experimental data on the energy loss dE/dx of protons in H{sub 2} and O{sub 2} have been sufficiently consistent to correct the results of the measurements of Bretscher, French and Sidel (Phys. Rev. 73, 815 (1948) and 75, 1154 (1949). Without describing the methods used to obtain the new data, the author uses the results of the dE/dx measurements to correct the cross sections of Bretscher et al. A simple correction factor is given, and the corrected values are tabulated for the D-D and D-T reactions. The Gamow formula, modified by a resonance factor, is applied to the revised data, and a good fit to the theoretical slope is obtained.

None

The intermediates of carbon dioxide reduction by plants include phosphorylated derivatives of hydroxy acids and sugars. Their identification becane possible when the use of labeled carbon dioxide permitted discrimination between the earliest products and the many other components of photosynthetic tissues. A number of compounds were identified by virtue of the chemical and physical properties of the radioactive compounds in tracer amounts and by direct comparison of these properties with those of suspected known metabolic intermediates. It became apparent that several labeled compounds found in short exposures to radioactive carbon dioxide were not substances previously identified as metabolic intermediates. Two phosphate esters in particular were observed in the products of the first few seconds of steady-state photosynthesis by all the photosynthetic microorganisms and higher plants examined in this laboratory. These esters have been isolated by paper chromatography in tracer quantities and enzymatically hydrolyzed to give two sugars, ribulose and sedoheptulose. This paper contains a description of the chemical identification of these sugars and some observations and suggestions regarding the function of their esters. The general importance of these compounds in photosynthesis was surmized before their identification. The products of photosynthesis with C{sup 14}O{sub 2} by each plant included phosphate esters …

None

None

None

None

In 1946, it was recommended, by the district engineer for the War Department, United States Engineer Office, that it was desirable to transfer all of the functions of production to Hanford, a production installation; thereby relieving the Argonne National Laboratory, a research installation, from production duties. This decision was based on the belief by Argonne National Laboratories that the principal problems of production were solved, as a result of a meeting held at Clinton Laboratories, October 25, 1946, during which, Dr. T.S. Chapman discussed with Major F.A. Valente the possibility of Hanford assuming full production responsibility for the product extracted from the irradiation of Special Request. This responsibility was to include the procurement of lithium fluoride, the preparation and canning of the pellets, the irradiation of the slugs, the extraction of the product and its subsequent shipment to the consumer. This report details historical aspects of this program and the P-10 Project.

Increases in power levels of the Hanford Piles have resulted in increased demands for process cooling water to the extent that the present filter plants are now operating at or above their design capacity. Further power level increases requiring even more cooling water may demand the operation of the filters considerably above design capacity. It has been proposed that by the use of aluminum sulfate, or filter alum, as a process water coagulant and activated silica as a coagulation aid, the present filter plant capacities could be increased appreciably. In order to investigate the effects of alum-treated water on pile operation, a full-pile production test was authorized in which alum was substituted for the standard ferric sulfate coagulant. This test was started in the 100-F Area on October 10, 1951. The results of the first thirty days of operation were presented in a previous report and served as a basis of the decision to proceed with installation of the activated silica addition facility. This report presents the data, results and conclusions obtained from the start of the test until its termination of December 28, 1951, when the addition of activated silica began.

The design will be based on one reactor with a potential capacity of 1,300 megawatts. For the time being this reactor will be designated ``X``. The water plant will be designed to supply 100,000 gpm initially. The design shall provide, however, for the ultimate capacity of 140,000 gpm; i.e., underground process piping, space in river pump house, and other items which would be difficult to enlarge after initial construction, will be sized for the ultimate capacity and provision shall be made for future enlargement of filter plants, etc. to provide the required increase in capacity.

None

To one whose responsibility it is to make evaluations of the degree of hazard existing in the radiation field of a nuclear accelerator or a nuclear reactor, the valid estimate of the contribution of neutrons to such a field is of considerable importance. The degree of difficulty of such a measurement depends strongly upon the information desired - whether (1) simply the presence of 'slow' and 'fast' neutrons in significant numbers is in question, or (2) a measure of flux densities within known energy intervals is required, or (3) a direct estimate of the specific rate of energy absorption due to neutron-produced effects in a given medium is desired. The importance of securing trustworthy estimates of the neutron field can be appreciated by recalling that the biological damage due to a given amount of ionization produced in biological tissue by effects due to neutrons is estimated to be several times the damage due to a similar amount of ionization produced by X-rays or gamma rays. This 'relative biological effectiveness' must be evaluated by carefully controlled animal experiments. Its value appears to range from about 2.5 for slow neutrons to abount 10 for fast and high energy neutrons. Of course the …

It is important that the design of the safety control system for RDA-DC3 be firmed up as soon as possible. This is necessary so that the detailed design of the graphite stack and other components can proceed. One design objective for RDA-DC-3 was the use of an all ball system for the safety system. The questionable feature of such a system from a mechanical and operating standpoint is the requirement that the balls be returned to the hoppers in about 10 minutes. This stringent requirement can be eliminated by having enough rods to provide control for shutdowns not involving severe emergencies and tripping balls only for those severe cases where rod control is not adequate. Any emergency which would trip the balls would be infrequent as well as so severe that the pile would be down for a period exceeding the minimum recovery time (about 30--45 minutes) and therefore would have to remain shut down for 30 hours or more. In such a case, the requirements for a ball return system can easily be met. The system proposed for RDA-DC-3 is a combination of about 60 ball slots with 35--40 rods.

This quarterly report details activities of chemical research by the Separations Technology Unit for the months of October, November, and December 1951.

This report addresses the density-weight percent molarity conversion equations for Uranyl sulfate-water solutions at 25°C and between 100-300°C.

None