A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the ERDA Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps has been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide the basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps has been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

Using the self-consistent solutions of the Eliashberg theory, the limitations on the superconducting critical temperature T/sub c/ of isotropic superconductors are discussed.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks.

The objective of this program was to continue the developmental effort aimed toward production of a composite conductor capable of carrying 10,000 A at 12 T and suitable for use in large fusion magnets. This program pertains specifically to the development of Nb/sub 3/Sn multifilamentary conductors containing tubular Nb filaments with Cu-Sn alloy cores in a high conductivity copper matrix. The specific tasks include: (1) Fabricate 1000 ft of 1000 A, 12 T conductor for coil evaluation. (2) Fabricate several lengths of 3500 A, 12 T conductors for evaluation. These samples are to contain the required copper and reinforcing material for use in a large coil. (3) Perform further experiments to optimize T/sub c/ with respect to Nb, Nb-1%Zr and the percent Sn composition in the bronze alloy. (4) Fabricate a 150 ft long sample of the optimum 3500 A, 12 T conductor following completion of Tasks 1, 2, and 3. (5) Fabricate several short test samples of 10,000 A, 12 T conductor for short sample and mechanical strain testing. (6) Furnish complete report containing the results of all tests performed, all metallurgical data and detailed descriptions of fabrication techniques used.

A set of OS/370 Basic Assembly Language programs is described which provides a FORTRAN IV interface with OS/370 Macros.

Vapor explosions were produced by injecting small quantities of water into a container filled with molten sodium chloride. Minimum explosion efficiencies, as evaluated from reaction-impulse measurements, were relatively large. Subsurface movies showed that the explosions resulted from a two-step sequence: an initial bulk-mixing phase in which the two liquids intermix on a large scale, but remain locally separated by an insulating gas-vapor layer; and a second step, immediately following breakdown of the gas layer, during which the two liquids locally fragment, intermix, and pressurize very rapidly. The experimental results were compared with various mechanistic models that had been proposed to explain vapor explosions. Early models seemed inconsistent with the results. More recent theories suggest that vapor explosions may be caused by a nucleation limit or by dynamic mixing combined with high surface-heat-transfer rates. Both types of models are consistent with the results.

Progress report describing the research and management efforts of Argonne National Laboratory's program on high-performance lithium/metal sulfide batteries during the period July-December 1975. The batteries are being developed for two applications: off-peak energy storage in electric utility networks and electric-vehicle propulsion. The battery designs for the two applications differ, particularly in cell configuration and electrode design because of the differing performance requirements.

A simple conduction model with phase change has been developed for the transient analysis of a fuel pin based on average properties and lumped-parameter techniques. The transient behavior of fuel and cladding can be accurately described by simple analytical expressions that agree with conventional numerical approaches for under-cooling transient analysis. If it be assumed that the heat-transfer resistance between the fuel and cladding remains the same for both steady-state and transient periods, the phase-change problem for fuel and cladding melting can be significantly simplified. BY using the predetermined average overall heat-transfer coefficient across a fuel pin in the steady-state period, the average transient fuel and cladding temperatures can be formulated analytically. For loss of flow at constant power, the start of melting and complete melting for both the fuel and cladding can be estimated with considerable accuracy.

The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-assessment methodology is outlined and proposed (accident-spectra-progression approach). The generalization consists primarily of an explicit treatment of uncertainties throughout the accident progression. The results of this method are obtained in form of consequence distributions. The width and shape of the distributions depend in part on the superposition of the uncertainties. The first moment of the consequence distribution gives an improved prediction of the ''average'' consequence. The higher-consequence moments can be used for consideration of risk aversion. The assessment of the risk of one or a certain number of nuclear reactors can only provide an ''isolated'' risk assessment. The general problem of safety risk assessment and its relation to public acceptance of certain modes of power production is a much broader problem area, which is also discussed.

Hydrogen from the radiolysis of water by dissolved fission products is stripped from the solution and collected by bubbling carbon dioxide through the solution. Quantitative measurements of the G value for hydrogen show that the yield is essentially the same as would be obtained by external gamma radiolysis of nonradioactive solutions of the same chemical composition. The hydrogen yield can be enhanced by addition of a hydrogen-atom donor, such as formic acid, to the solution. The yield of hydrogen from fission-waste solutions is discussed with respect to the question of whether it represents a significant energy source.

Studies of unprotected loss-of-flow accidents in the CRBR for various rates of flow coast-down and with various options in the SAS 3A code did not lead to conditions for a violent disassembly. Maximum fuel temperatures using the SLUMPY module for disassembly were in the range 4000-4500 deg C. An approximate treatment of the LOF-driven TOP accident, not properly modeled by SAS 3A, indicates the possibility of some increase in accident severity. The effect of fission gas in dispersing fuel was not taken into account in these calculations. Parameter variations included the presence or absence of axial fuel expansion and of clad motion and use of the moving coolant film model versus the static film model. Study of severe pipe rupture accidents with scram indicated that pin power density and fuel-clad conductance were important parameters in determining what coolant flow rate was needed to prevent boiling after the rupture. It appears that for the CRBR when engineering hot channel factors are considered, this fraction would have to exceed 25 percent.

During operation of the prototype FFTF sodium pump, it is necessary to know the position of the pump shaft relative to the sodium-lubricated hydrostatic bearing journals. Performance of the Kaman proximity measurement system was known to be affected by the type of media between the gap to be measured. Since Kaman Sciences Corp. did not have liquid sodium testing capabilities, LMEC was requested to evaluate a spare prototype system. Determination of the sodium performance characteristics of the Kaman proximity systems was a necessary requisite for use of four prototype systems in the FFTF prototype pump test program.

The authors have examined 1200 interactions with visible energies greater than 7.5 GeV produced by an anti-neutrino beam in the Fermilab 15-foot bubble chamber filled with a light neon hydrogen mixture. They have found one event with a {mu}{sup +}e{sup -} and hadrons in the final state, but with no evidence of strange particle production. This event may be an example of dilepton production by an anti-neutrino interaction, but other interpretations are possible. With 90% confidence, they conclude that the rate for the process {bar {nu}} + N {yields} e{sup -} + {mu}{sup +} + hadrons is {le} .8% of charged current anti-neutrino interactions with visible energy > 7.5 GeV.

Summaries of ten research projects are presented. They include: equations describing various geothermal systems, geohydrological environmental effects of geothermal power production, simulation of linear bench-scale experiments, simulation of fluid-rock interactions in a geothermal basin, geopressured geothermal reservoir simulator, user-oriented geothermal reservoir simulator, geothermal well test analyses, geothermal seismic exploration, high resolution seismic mapping of a geothermal reservoir, experimental evaluation of geothermal well logging cables, and list of publications. (MHR)

The preliminary analysis is described in a study of practical cycles for geothermal power plants. The analysis is based on three different brines whose temperatures and composition span the range that is of practical interest for power generation. Only two kinds of cycles were considered in the analysis - the steam turbine cycle and the binary cycle, in which energy from the geothermal fluid is transferred to a secondary working fluid in a closed Rankine cycle. The performance of several condidate working fluids has been investigated, and the most attracive binary cycles have been selected for the various resource conditions. The results show that if brine is utilized directly in the primary heat exchange process with the secondary working fluid, the binary cycle is potentially better in terms of resource utilization than a dual flash steam turbine cycle. However, if the brine is flashed to steam and the steam is used for the heat exchange process, the steam turbine cycle will produce more power per pound of brine flow. Preliminary turbine designs have been formulated for steam and also for the most promising working fluids in the secondary or binary cycle. For all cycle configurations at least 50 MW of …

A system of regional operations research activities is described which will formulate potential future development scenarios for geothermal energy and identify the public initiatives necessary for that potential. The specifics of the work plan for the state of California are outlined along with the project management structure and reporting schedules. (MHR)

Sodium-cladding chemical interaction has been studied on fuel pins clad with 20% cold worked type 316 stainless steel and irradiated in the EBR-II at temperatures up to 705/sup 0/C and for exposures to 5300 hours. The measured corrosion rate of the cladding surface immediately above the top of the fuel column was 12.5 ..mu..m per year at 690/sup 0/C. The loss of Ni at 700/sup 0/C resulted in the formation of a ferrite layer approximately 5 ..mu..m thick. A zone depleted in Ni and Cr extends into the austenite from the ferrite-austenite interface an additional distance of approximately 15 ..mu..m. No large changes in volumetric average carbon or nitrogen were observed.

The effects of lateral mass efflux with prescribed temperature and velocity on vertical free convection boundary layers in a saturated porous medium at high Rayleigh numbers are studied analytically. Within the framework of boundary layer theory, similarity solutions are obtained for the special case where the prescribed temperature and velocity of the fluid vary as x/sup lambda/ and x/sup (lambda-1)/2/ respectively. The effects of mass efflux on surface heat transfer rate and boundary layer thickness are shown. Application to warm water discharge along a well or fissure to an aquifer of infinite extent is discussed.