None

The techniques for assembling, processing and handling large nuclear-emulsion stacks are discussed. Results of experiments varying the development procedure are presented.

The design basis is composed of requirements and conditions for the design of the reactor plant (composed of the reactor and heat dissipation system). Its intent is to insure that the final product meets the economic, safety, and technical objectives of the project. The design basis is dependent on the ground rules, objectives, technical criteria, and practical design considerations. This document is being issued with the understanding that these items are not yet firmly established in all respects, and therefore, the numbers put down here are subject to change. Consideration of the spectrum of probable changes that might be made leads to the conclusion that the numbers here are close to the final ones and are satisfactory as a basis for the initial stages of design. Some numbers are omitted because of insufficient data at this time.

This report discusses activities from the fuels processing department. Activities described include personnel statistics concerning injuries and accidents; operating plans concerning the N loading activities, 305 test reactor, projection fuel elements; process fuel element testing, and general engineering operations from the department.

In reviewing the data on hydrogen content in the canning baths, the solubility limit of H{sub 2} in Al-Si, and the U-H{sub 2} relationship as was suggested earlier, it appears that the surface H{sub 2} on the core should be less than 0.4 ppm to be below the H{sub 2} concentration level routinely found in the canning baths. What effect low surface H{sub 2} of about 0.4 ppm would have on braze porosity after canning is unknown. However, several years ago (about 1955) some solid cores were vacuum outgassed at MAPO to about 0.5 ppm total H{sub 2} and very little braze porosity resulted.

This report discusses a comparative irradiation test of fuel elements of N-fuel uranium composition at Hanford.

The Purex L-Cell Package is used for organic stripping and concentrating aqueous plutonium solutions from the final Pu solvent extraction decontamination cycle. At the present time the package is used only during times when the gamma activity of the final product is too high to permit routing the solution to N Cell for final ion-exchange purification or when N Cell is inoperative. The package can be used only to concentrate and then route solutions to the PR Room for loadout into PR cans for storage prior to rework via TK-E6. In addition, operating data have shown that the present package has a low boil-off capacity which is insufficient for both current and forecasted plant production rates. At the present time, flowsheet modifications and processing rate reductions are necessary when the package is in operation. Entry into L Cell and contact maintenance are required to maintain the present package which was installed in 1956. Repairs to the package were made in 1962, and information obtained at that time indicates that extensive repairs to the present package will be required in the near future. The purpose of this report is to present the engineering study for the required modifications to the package …

This document details activities of the N-Reactor Department during the month of August 1964.

Short-time tensile tests were conducted on irradiated (2 x 10/sup 20/ nvt) and unirradiated Hastelloy-N bar from heats 5911 and 6252. No significant difference in mechanical properties was noted between the two heats. The 1200/sup 0/F ultimate tensile strength was decreased by irradiation from 65 to 80 ksi and 48 to 52 ksi. The 1400/sup 0/F ultimate tensile strength was decreased from 45 to 51 ksi to 32 to 34 ksi. The yield strength was not greatly affected by irradiation at either 1200 or 1400/sup 0/F. The 1200/sup 0/F elongation at fracture was decreased from 15 to 45% to 5 to 11%. The 1400/sup 0/F ductility was decreased from 8 to 26% to 1 to 1-1/2%. Unirradiated uniaxial stress-rupture tests were conducted at both AI and ORNL. No definite difference in stress-rupture properties between heats was noted at either 1200 or 1400/sup 0/F in ORNL tests, although some of the 1400/sup 0/F stress-rupture tests indicated that heat 6252 exhibited greater ductility. The AI verification tests showed a definite ductility difference, with heat 6252 exhibiting greater ductility. This phenomenon was attributed to an inhibition in crack propagation due to microsegregation.

This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic·Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during August 1969 .

None

A high-purity germanium (HPGe) array, photon-counting system has been developed for the Rocky Flats Plant Body-Counter Medical Facility. The newly improved system provides exceptional resolutions of low-energy X-ray and gamma-ray spectra associated with the in vivo deposition of plutonium and americium. Described are the operational parameters of the system and some qualitative results illustrating detector performance for the photon emissions produced from the decay of plutonium and americium between energy ranges from 10 to 100 kiloelectron volts. Since large amounts of data are easily generated with the system, data storage, analysis, and computer software developments continue to be an essential ingredient for processing spectral data obtained from the detectors. Absence of quantitative data is intentional. The primary concern of the study was to evaluate the effects of the various physical and electronic operational parameters before adding those related entirely to a human subject.

A variety of systems are required for adequate diagnostics of laser fusion experiments. Picosecond scale temporal measurements are typically made with ultrafast streak cameras. Visible and x-ray sensitive streak cameras with resolutions of 6 psec and 15 psec, respectively, and dynamic recording range in excess of 10/sup 3/ are in regular use on experiments at Livermore. The characteristics of these cameras and their applications to target experiment diagnostics are described. The development and testing of a prototype ultrafast framing system is discussed. Because of the need for ''real time'' data acquisition, analysis, and control systems, techniques for providing directly computer interfaced image data from streak and framing cameras and optical imaging systems are being developed. The status of these developments and the characteristics of the computer interfaced data and control systems on Argus and Shiva are summarized.

Various schemes for obtaining anti pp interactions are outlined, and the luminosities obtainable for each case calculated. In the simplest realistic case, a luminosity of 1.3 x 10/sup 29/ is obtained with a 13 hour filling time. The addition of special rf systems in both the AGS and ISABELLE give a scheme with luminosity 8 x 10/sup 29/ in 6 hours. The use of stochastic cooling to stack raises the luminosity to as high as 10/sup 31/ but the filling time is then 68 hours. Finally a scheme is considered that uses a special 30 GeV capture ring. With this, a luminosity of 10/sup 31/ could be achieved after 20 hours, or higher if a larger filling time were acceptable. Further gains could be made if a smaller proton spot on the target is used but a simple calculation suggests that even the spot size assumed may explode the target too fast.

This standard establishes the requirements for fabrication, testing, and inspection of control rod assemblies for use in liquid metal fast breeder reactors.

Along the general run of the vacuum chamber synchrotron radiation strikes the wall at a glancing angle of about 5.6/sup 0/. The heat source is well-approximated by a ribbon of uniform power density having a small vertical height and an infinite azimuthal length. The heat transfer problem reduces to one in two-dimensions and it has been considered in a previous note. At the corner of a beam port the angle of incidence becomes 90/sup 0/, so the temperature rises much higher than elsewhere. Since the power density at the corner is not uniform in its azimuthal dependence, but is strongly peaked at the point of normal incidence, two-dimensional heat flow is not a good approximation. The rectangular 3d problem is considered. This is easily solved and yields a good first estimate of the temperature rise at the corner.

A critical review of U.S. and foreign literature on the use of a mixture of refrigerants rather than a single one in a refrigeration unit indicates that energy can be conserved in properly arranged systems. An independent analytical study performed under the current contract using a 50% mixture of R-12 and R-114 in a two-evaporator refrigerator typical of domestic refrigerators showed an energy saving of 12%. The cycle explored was a non-optimized one, so greater energy savings are theoretically possible. The application of refrigerant mixtures to domestic refrigerators would not be a panacea, but would require a redesign of the refrigeration circuit and a resizing of the compressor. There would be a number of problems to be explored and solved before a successful application could be achieved, but the prospects look favorable at this time. One of the most useful next steps would be to continue to expand the knowledge base on refrigerant mixtures that would be made available to the manufacturers of refrigerators.

The Morgantown Energy Technology Center (METC) is developing the technology required to recover the deep thin seam Eastern bituminous coal resource by gasification in-situ. The approach is to prove concepts through field tests and to support field testing-with theoretical modeling. METC is currently fielding Pricetown I, the first of two tests scheduled for the Pricetown, West Virginia, underground coal gasification field test. Pricetown I is a small-scale test designed to provide information concerning the in-situ characteristics of the Pittsburgh coal seam; to gain additional experience in the in-situ combustion and gasification of bituminous coal; and to evaluate the functional applicability of the linked vertical concept to recover the Eastern resources. Mound Facility is participating with METC in the design and the implementation of the instrumentation necessary to monitor the surface and subsurface process and product gas stream; and acquire real-time gas analysis and subsurface thermal data. The principal objective of this effort is to provide an integrated instrumentation system that will permit rapid automatic monitoring of subsurface and surface variables and to ensure data storage, retrieval and reduction for process monitoring and results interpretation. Mound also will support METC with the manpower and technical assistance necessary to operate the field …

The MFTF is a large new mirror facility under construction at Livermore for completion in 1981--82. It represents a scaleup, by a factor of 50 in plasma volume, a factor of 5 or more in ion energy, and a factor of 4 in magnetic field intensity over the Livermore 2XIIB experiment. Its magnet, employing superconducting NbTi windings, is of Yin-Yang form and will weigh 200 tons. MFTF will be driven by neutral beams of two levels of current and energy: 1000 amperes of 20 keV (accelerating potential) pulsed beams for plasma startup; 750 amperes of 80 keV beams of 0.5 second duration for temperature buildup and plasma sustainment. Two operating modes for MFTF are envisaged: The first is operation as a conventional mirror cell with n/sup tau/ approximately equal to 10/sup 12/ cm/sup -3/ sec, W/sub i/ = 50 keV, where the emphasis will be on studying the physics of mirror cells, particularly the issues of improved techniques of stabilization against ion cyclotron modes and of maximization of the electron temperature. The second possible mode is the further study of the Field Reversed Mirror idea, using high current neutral beams to sustain the field-reversed state. Anticipating success in the coming …

Since the earliest days of fusion research it has been hoped that diamagnetic currents flowing in a plasma could be used to help confine the plasma. Recently this hope has been strengthened both by theoretical advances and by experimental results made possible by technological developments. On the theoretical front analytical treatments and computer simulation studies have demonstrated equilibrium solutions existing both in the fluid limit and in the large-orbit limit. Progress has also been made in determining the conditions required for the stability of field-reversed entities. It appears that configurations of the general form of fat doughnuts, possibly elongated to napkin-ring form, represent stable states. Building on previous experimental work, several investigators have been able to create field-reversed states. One method, based on the ASTRON idea of Christofilos, traps an intense relativistic electron beams (REB) to create a field-reversing current ring. Other approaches use either the reversed field theta pinch technique or REB pulses to create field-reversing diamagnetic currents in a long cylindrical plasma. In the former method, millisecond-long field-reversing electron rings have been achieved; in the latter method field-reversed plasma states lasting 30 to 50 microseconds have been achieved. Another approach under investigation is the Field Reversed Mirror (FRM) …

The cavity design for the large ring of the proposed synchrotron light source is being considered. It represents the worst case situation in all respects so that a similar design for the small ring will face no problems. Basic requirements are that the cavity provide a peak gap voltage of up to 500 kV at a frequency of 53.52 MHz. Sufficient tuning range must be provided to allow for the reactive detuning of the beam and also thermal changes. Provisions for phase and amplitude control of two cavities operating together must also be available and attention must be given to possible higher order mode excitation at frequencies which are harmonically related to the operating frequency and also to some degree the 2.23 MHz rotation frequency. There are also space limitations imposed by the chosen magnet lattice and the need for a beam wiggler in the same straight section as the rf cavity. The practical upper limits of cavity diameter and length are about 1.25 m and 1.7 m, respectively.

Inconel 600 was irradiated in HFIR to provide a partial simulation of fusion reactor service. Samples were irradiated at 55 to 700/sup 0/C, to investigate swelling and postirradiation tensile properties as a function of irradiation and test temperatures under conditions of concurrent displacement damage and helium production. Helium contents from 600 to 1800 appm and displacement levels of 4 to 9 dpa were achieved, and the results are used to estimate performance in a fusion reactor environment. Tensile property measurements and fractography on the same samples showed strength values increased for irradiation at 55 to 400/sup 0/C but decreased below unirradiated values for irradiations at 600 and 700/sup 0/C.

Geothermal studies are proceedings on two fronts in the West Yellowstone area. High-temperature resources for the generation of electricity are being sought in the Island Park area, and lower temperatures resources for direct applications, primarily space heating, are being explored for near the town of West Yellowstone. Potential electric geothermal development in the Island Park area has been the subject of widespread publicity over fears of damage to thermal features in Yellowstone Park. At the time of writing this guide, companies have applied for geothermal leases in the Island Park area, but these leases have not yet been granted by the US Forest Service. The Senate is now discussing a bill that would regulate geothermal development in Island Park; outcome of this debate will determine the course of action on the lease applications. The Island Park area was the site of two cycles of caldera activity, with major eruptions at 2.0 and 1.2 million years ago. The US Geological Survey estimates that 16,850 x 10{sup 18} joules of energy may remain in the system. Geothermal resources suitable for direct applications are being sought in the West Yellowstone vicinity by the Montana Bureau of Mines and Geology, under funding from the …

The model PA-720 Automatic Particle Size Analyzer is a simple, relatively high speed device designed to provide accurate size distributions in both tabular and graphic forms. This model has two dynamic ranges; 50 to 2500 microns and 200 to 1600 microns. This is an abbreviated version of the manufacturer's operating manual. It provides all the necessary information for the novice and experienced user. For more detailed explanations and servicing procedures one should reference the full manual.