This report discusses progress on the following topics: (1) some new isotopes in the rare earth region; (2) remarks on a new alpha series; (3) solid counters; (4) naphthalene crystals have been replaced with anthracite in one of the experimental counters and some excellent results are obtained; and (5) biological experiments with the deuteron bean of the 184-inch cyclotron.

This report details events of importance reported by the Hanford Operations Office for the week ending April 6, 1949.

Minutes of conferences held at Chalk River, Ontario. The subjects discussed related primarily to separations processes.

A high-density concrete shield is proposed for the biological shield. Adequate shielding of personnel and equipment can be obtained for about two-fifths the cost of a laminated shield of steel and masonite. The proposed shield is expected to behave satisfactorily during the life of the Reactor Unit and, in addition, the shield will possess considerable resistance to earthquake and blast loads. Details of design specification are given.

Since 1945 the routine production of plutonium (``A`` buttons) at Atomic Energy plants has been accomplished by heating mixtures of plutonium tetrafluoride, calcium and iodine in crucible-bomb assemblies. Yields above 97% and metal of adequate purity are consistently obtained by this process. Plutonium (``X`` button) production has also been carried out routinely by including plutonium turnings with the powder mixture given above. A majority (several thousand) of buttons produced in the 234-5 Building have been ``X`` buttons made by recycling up to 1.1 units of turnings/unit of plutonium in the plutonium tetrafluoride. Operating hazards exist in either process, however, and these are reviewed below.

None

This Hanford-General Electric Report to the Working Committee details activities in fuel element fabrication, canning, and testing during this reporting period.

A design was developed for leading thermocouples from a high-temperature, pressurized water reactor-coolant system of such integrity that no reactor shutdowns were caused by its use. Using this design, measurements of the fuel-element-cladding temperature and its variation with time were made in three tests on elements clad in type X-8001 aluminum alloy. The following conclusions were reached from the test results: (1) the cladding temperature of a fuel element operated at low heat flux in high bulk-outlet temperature water did not increase with time and was slightly lower than predicted by the Sieder-Tate equation; (2) cladding temperatures of fuel elements operated at high heat flux in either high bulk-inlet or outlet temperature water increased 40 C higher than predicted by the Sieder-Tate equation with initial temperatures equal to the predicted temperatures; and (3) the rate of temperature increase appeared dependent only on fuel-element heat flux and location with respect to the front and rear faces of the reactor.

The loss associated with low goaling rupture-prone material is quite small compared to the benefits. There is an optimum goal exposure for a given metal quality. At this optimum exposure the loss associated with irradiating rupture-prone material is minimized. Reasonable decision rules are as follows: Discharge, at the first opportunity, tubes containing rupture-prone material whose exposures are equal to or greater than 50 percent of normal goal. Discharge tubes under 50 percent of normal goal which would be expected to reach 70 percent of normal goal before the next scheduled outage. Irradiate all tubes containing rupture-prone material whose exposures will not be expected to exceed 70 percent of normal goal before the next scheduled outage. Discharge all tubes containing rupture-prone material, regardless of exposure, if an additional rupture is incurred in the lot. Return unirradiated rupture-prone material to Production Fuels Section as reject material.

This document details activities of the N-Reactor Department during the month of March 1963.

This report is divided into: present reactor fuel production, NRD production fuels, N fuel development, and current reactor fuel development.

The scheduled termination of PT IP-659-AC, presently being irradiated in F Reactor, will result in discharge of 105 columns of enriched uranium (0.947 w/o U-235) at less than 50 per cent of the goal exposure. The test block is currently scheduled to be replaced with natural uranium columns. Since F Reactor is on a semiblock discharge plan (alternate rows), subsequent operating plans would require that 64 of these replacement columns of natural uranium be likewise discharged during the scheduled outage in May of 1964 at less than 50 per cent of goal. It appears desirable to minimize the economic costs of the production test by an alternative discharge scheme (e.g., interim poison irradiation). The objective of this supplement is to soften the economic impact of low exposure fuel discharge scheduled by IP-659-AC and simultaneously to obtain a useful alternate product by irradiating nine columns of Li-Al and Bismuth in a ``striped`` charge.

Heat discharged to the Columbia River in reactor cooling water is one of the more important pollutants from Hanford operations. The effect of this heat on river temperatures has been studied for several years, primarily because of the potential effect on the Columbia River fisheries. This document presents a summary of recent river temperature experience, with comparison data for a better perspective.

Plant construction costs and manufacturing costs have been estimated for the production of solar-grade silicon by the reduction of silicon tetrachloride in a fluidized bed of seed particles, and several modifications of the iodide process using either thermal decomposition on heated filaments (rods) or hydrogen reduction in a fluidized bed of seed particles. The objective was to evaluate the economics of the zinc reduction process and to determine whether any of the potential economies in the modifications of the iodide process would make it competitive in spite of the high relative cost of recycled iodine in the process intermediate. The estimated cost of the zinc reduction process, $9.12 kg/sup -1/ silicon is within the target of $10.00 kg/sup -1/; however, none of the modifications of the iodide processes yielded costs below $20 kg/sup -1/ Si. Although optimization of one of the iodide process modifications should bring the cost to below $20 kg/sup -1/ Si, it would not be possible to reduce the cost to below that of the zinc reduction product. Energy consumption data for the zinc reduction process and each of the iodide process options are given and all appear to be acceptable from the standpoint of energy pay …

The objective of the High Temperature Electronics Program is the assembly and/or development of the technologies necessary for the fabrication of measurement and communications electronics operative in a 500/sup 0/C ambient. It is anticipated that the technology will be developed to the level required to demonstrate medium scale integrated circuits. Basic electronic properties, structures, and fabrication technology for gallium phosphide and silicon carbide devices are presented. (TFD)

A dynamic model was set up to determine the fundamental frequencies of the BIPS. The model consists of a radiator which supports four discrete masses by means of interface structures. Various materials and several different sizes of interface structures were used in the analysis. The fundamental frequencies vary from 38 cps to 227 cps dependent upon the material and the size of interface structure. The built-in strength of all the interface structures are in excess of the 25 g's limit loading criteria.

The Lawrence Livermore Laboratory has been appointed by the U.S. Energy Research and Development Administration to be the lead laboratory for carrying out a long-term project to acquire complete understanding of the environmental quality in the Imperial Valley of California prior to any major developments. The purpose of this project is to ensure that the development of geothermal resources proceeds on an environmentally sound basis. Consequently, the Imperial Valley Environmental Project (IVP) is committed to an intensive and comprehensive study designed to establish an environmental baseline for the Imperial Valley as well as to develop an understanding of the environmental and other effects associated with development of geothermal resources. The IVP is organized into seven main study sections, which when taken together cover all the significant issues and concerns. The sections are: Air Quality; Water Quality; Ecosystem Quality (Soil, Plants, Animals, etc.); Subsidence and Induced Seismicity; Health Effects; Socio-Economics; and an Integrated Assessment. (auth)

Growth of channel catfish (Ictalurus punctatus) and Tilapia zillii in the Reft River Geothermal Area (RRGT) geothermal waters can equal or surpass that in a commercial aquaculture facility. Fish and prawn mortality over the course of the intermediate term preliminary study did not appear to be related to any inherent geothermal water chemistry conditions. Temperature control was a problem but does not appear to be beyond design control. The absence of temperature-related mortality in channel catfish, Tilapia zilli, and yellow perch (Perca flavescens) indicates increased survival and suggests reduced expenditures for disease control. It may also allow higher fish densities in commercial aquaculture operations using geothermal water. Results of this study indicate potential for commercial aquaculture development at the Raft River Geothermal Testing Site.

A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable.

The objectives of this research project were to obtain data on the behavior of potentially toxic substances introduced into surface waters from nuclear power plants, determine the impact magnitude of these substances on representative and economically important aquatic species, and the development of models with which to predict the partitioning of these substances among the abiotic aquatic compartments. Results are included from an investigation of copper partitioning in freshwater and seawater, the toxicity of copper to representative marine organisms, and development of a mathematical model to predict copper partitioning.

The objective of this program is to design, fabricate and demonstrate an automated solar cell module production line with the ultimate goal of reducing module assembly costs. During this reporting period the automated module design was completed. The design of the solar cell assembly prototype (SCAP) was about 75% completed and the solar panel lamination prototype (SPLP) was built and tested.

Chem Systems is carrying out an experimental program for the conversion of coal-derived synthesis gases to a mixture of C/sub 1/-C/sub 4/ alcohols. The objectives of this contract are to: (1) develop a catalyst and reactor system for producing a mixture of C/sub 1/-C/sub 4/ alcohols, which we call Alkanol fuel, to be used as a synthetic transportation fuel and (2) assess the technical and economic feasibility of scaling the process concept to a commercial-scale application. Some of the accomplishments made this quarter were: (1) a small (75cc) fixed-bed, plug-flow, vapor phase reaction system was set up and operated utilizing catalyst bed dilution with inert media to help limit the large exotherm associated with the synthesis gas conversion reactions; (2) a total of fifteen (15) catalysts containing varying amounts of Cu, Co, Zn, Cr and K were prepared and seven of these catalysts were tested; (3) we have identified at least one promising catalyst composition which has resulted in a 30% conversion of carbon monoxide per pass (synthesis gas had a 3.5 H/sub 2//CO ratio) with a carbon selectivity to alcohols of about 80%.

A Reticon 50 x 50 photodiode array camera has been placed on Livermore's Tandem Mirror Experiment to view a 56-cm diameter plasma source of visible, vacuum-ultraviolet, and x-ray photons. The compact camera views the source through a pinhole, filters, a fiber optic coupler, a microchannel plate intensifier (MCPI), and a reducer. The images are digitized (at 3.3 MHz) and stored in a large, high-speed memory that has a capacity of 45 images. A local LSI-11 microprocessor provides immediate processing and display of the data. The data are also stored on floppy disks that can be further processed on the large Livermore Computer System. The temporal resolution is limited by the fastest MCPI gate. The number of images recorded is determined by the read-out time of the Reticon camera (minimum 0.9 msec). The spatial resolution of approximately 1.4 cm is fixed by the geometry and the pinhole of 0.025 cm. Typical high-quality color representation of some plasma images are included.

The objective of the Hot Corrosion Project in the LLNL Metals and Ceramics Division is to study the physical and chemical mechanisms of corrosion of nickel, iron, and some of their alloys when these metals are subjected to oxidizing or sulfidizing environments at temperatures between 850 and 950/sup 0/C. To obtain meaningful data in this study, we must rigidly control many parameters. Parameters are discussed and the methods chosen to control them in this laboratory. Some of the mechanics and manipulative procedures that are specifically related to data access and repeatability are covered. The method of recording and processing the data from each experiment using an LS-11 minicomputer are described. The analytical procedures used to evaluate the specimens after the corrosion tests are enumerated and discussed.