Research has been carried out in two broad areas, nonlinear saturation of instabilities in collisionless plasma and incorporation of important physical phenomena into linear stability theories appropriate to Tokamaks. The nonlinear work has established a general technique for dealing with the singular functions which arise and is now applied to the collisionless drift, the dissipative trapped electron in linear geometry and the drift cyclotron loss cone. Multimode problems are under study. The linear theory includes the influence of resonant electrons on the trapped electron instability in sheared magnetic fields. A further calculation includes the collisional broading of the untrapped electron response. Finally a general technique is developed for calculations when there are collisions and the product of the poloidal wave number and ion gyroradium is not necessarily small.

Chemical getters can be used to scavenge tritium from inert gases. Cerium, which forms a hydride with a low dissociation pressure, has high reactivity, and is relatively inexpensive, is a good candidate getter material for such a scavenger system. Mathematical models for using cerium in both fixed- and fluidized-bed reactors predict satisfactory performance. Moreover, the capital cost of a gettering system, estimated to be between $115,000 and $166,000 (m/sup 3//s) flow, is competitive with that of the conventional catalytic-oxidation molecular-sieve system ($330,000/m/sup 3//s) now used. The gettering concept, therefore, warrants further investigation. This report assesses the feasibility of such a system.

Major improvements have been made to decrease the tritium release potential for LLL's tritium-handling facilities in Bldg. 331. Some of the major problems and solutions in designing and building the High Pressure Gas System, which was the first system to be rebuilt are described. To increase system safety, it was necessary to specify material and processes used in component manufacture, to inspect all materials and processes to ensure compliance with specifications, to use proper joint design, to use secondary containment in cases where specifications could not be met, and to exercise tighter control of operating procedures.

CO methanantion rates have been measured in the all-glass internal recycle reactor developed for this work. The methanation rate over the cylinder Ni film catalyst at 400/sup 0/C is 3.9 sec/sup -1/ initially, and the catalyst undergoes deactivation to a value of 1.8 sec/sup -1/, comparable with a reported value of 2.5 sec/sup -1/. The activation energy for Ni film on alumina is 24 kcal/mole, that for Ni film on silica is 17.8 kcal/mole comparable to values for Ni on these supports. The kinetics suggest that CO dissociation is rate limiting; carbon on the Ni is easily hydrogenated off. H/sub 2/S causes severe deactivation and regeneration after sulfur poisoning is not easily achieved by oxidation in the reactor. However, sulfur is easily removed from Ni by oxygen from a molecular leak in the high-vacuum chamber of the Auger electron spectrometer. Atmospheric pressure studies using an ante-chamber connected to the spectrometer chamber show that sulfur cannot be removed from Ni under conditions similar to those in the reactor because of rapid oxide growth which buries the sulfur preventing removal. Standards allowing determination of concentration as well as chemical state for Ni, O, S, and C have been developed.

Research on the use of cements in radioactive waste isolation is reported. Other research is reported on the effects of thermal treatments of clays and shales on their cation exchange capacities and relative sorptive properties for cations. Development of instrumentation for measuring thermal properties of cements at atmospheric pressure was completed. A method was developed for measuring heat flow in shales and cement. Data on thermodynamic properties of cements and shales are included. Studies of shales, siltstones, and evaporites including scanning electron microscopy are in progress. (JRD)

Deposition of solids at the wall of a nozzle used to expand geothermal brine may be accounted for by a hydrodynamic model describing eddy formation near the wall. A conceptual design of a nozzle with injection of an annular ring of fluid at the wall is presented.

A preliminary Failure Modes, Effects and Criticality Analysis (FMECA) for the BIPS Flight System (FS) was published as AiResearch Report 76-311709 dated January 12, 1976. The FMECA presented a thorough review of the conceptual BIPS FS to identify areas of concern and activities necessary to avoid premature failures. In order to assure that the actions recommended by the FMECA are effected in both the FS and the Ground Demonstration System (GDS), a checklist (the BIPS-DIC) was prepared for the probability of occurrence of those failure modes that rated highest in criticality ranking. This checklist was circulated as an attachment to AiResearch Coordination Memo No. BIPS-GDS-A0106 dated January 23, 1976. The Brayton Isotope Power System-Design Integrity Checklist (BIPS-DIC) has been revised and is presented. Additional entries have been added that reference failure modes determined to rank highest in criticality ranking. The checklist will be updated periodically.

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A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening.

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to …

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this …

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

Hamiltonian methods are used to study the motion of a particle in the field BZ and a single electrostatic wave. The particle motion is studied by numerically integrating the equations of motion. Diagrams of various particle trajectories are given. (MOW)

The following samples were irradiated with the LLL rotating target neutron source: 19-core Nb/sub 3/Sn multifilament wires, Nb/sub 3/Sn single core, V/sub 3/Ga single core, NbTi Supercon 402, and NbTi cupronickel jacketed. No test results are given. (MOW)

Electrical noise interference in low-level (approximately 50 ..mu..V), wide band (approximately 15 MHz) flux monitoring systems applied to nuclear reactor control causes safety and reliability problems. Others have shown that one predominant source of noise interference is conduction of currents in instrument cable shields and building conduits. Since these currents produce noise that is similar to signals produced by nuclear detectors, such noise interference reduces the ability of a reactor instrumentation system to determine the condition of a reactor. Model equations of ground noise interference were derived for a system model consisting of a sensor, coaxial cable, and an amplifier. These equations describe the effect of ground impedance, sensor impedance, transfer impedance, and connector resistance on both low-frequency (less than 100 kHz) and high-frequency (greater than 100 kHz) ground noise interference. Other model equations were derived for a system with a coaxial balun (a flexible coaxial cable wound around a ferrite core) added between the sensor and the sensor amplifier input. Analysis of the model equations reveals the effects of ground noise currents on instrumentation systems and the conditions for minimizing ground interference.

It is shown that substantial amounts of untransformed austenite may be obtained in low alloy steels by a combination of alloy modification (addition of silicon) and heat treatment. In silicon modified AISI 4330 steel, the amount of untransformed austenite is varied by utilizing isothermal treatments both above and below the M/sub s/. The stability of the untransformed austenite is found to be dependent on the amount of silicon and also on the tempering temperature. A magnetic saturation technique was utilized to monitor the transformation of the austenite under uniaxial tensile loading. An improvement in the plane strain fracture toughness (K/sub Ic/) was observed when the retained austenite transformed with respect to strain. This improvement was optimized with particular combinations of stability and volume fractions of retained austenite. The addition of silicon resulted in an increase of both the strength and the fracture toughness (K/sub Ic/) of the quenched and tempered AISI 4330 steel. Yield strengths in the range of 200-220 ksi and K/sub Ic/ values as high as 107 ksi..sqrt..in were obtained. The microstructure was characterized using both optical and electron microscopy and is correlated with the mechanical properties.

We subjected the Meteorological Data Acquisition (MEDA) remote station hardware to temperature, vibration, and road tests. The MEDA equipment was designed at the Lawrence Livermore Laboratory (LLL) for the Air Resources Laboratory (ARL). ARL supplied all MEDA sensors. The prototype system passed these tests.

Two methods of dust-flux measurements are discussed which have been utilized to estimate aerosol plutonium deposition and resuspension. In previous studies the methods were found to be sufficiently detailed to permit parameterization of dust-flux to the erodibility of the soil, and a seventh-power dependency of dust-flux (or plutonium flux) to wind speed was observed in worst case conditions. The eddy-correlation method is technically more difficult, requires high-speed data acquisition, and requires an instrument response time better than one second, but the eddy-correlation method has been shown feasible with new fast-response sensors, and it is more useful in limited areas because it can be used as a probe. The flux-gradient method is limited by critical assumptions and is more bulky, but the method is more commonly used and accepted. The best approach is to use both methods simultaneously. It is suggested that several questions should be investigated by the methods, such as saltation stimulation of dust-flux, simultaneous suspension and deposition, foliar deposition and trapping, erodibility of crusted surfaces, and horizontally heterogeneous erodibility.

Development of a high-intensity source for use in time-domain electromagnetic (TDEM) soundings would permit investigation of geothermal systems to much greater depth than is now possible with controlled-source methods. The development of such a source is critically dependent upon a powerful, mobile generator. Magnetohydrodynamic pulse generators satisfy the weight and power requirements for such a generator. However, existing MHD generators which are used in geophysical applications are solid fueled, and therefore, very expensive to operate. Moreover, the pulse length from such a generator is limited to about 10 seconds, which may be too short to permit the maximum advantage to be gained from the available power. The shortcomings of the MHD generator will be remedied in a liquid-fueled generator now under development for the U.S. Air Force. A field program designed to compare available conventional and MHD generators would provide the necessary information for final generator selection, as well as an abundance of information on the nature of geothermal systems at depth. Operation and cost studies on MHD generators are given, and model calculations for TDEM soundings of geothermal hot-dry-rock systems are presented.

A glass direct contact heat exchange column was operated in the laboratory at atmospheric pressure using hot water and normal hexane. Column internals tested included an empty column, sieve trays, disk-and-doughnut trays, and two types of packing. Operation was very smooth in all cases and the minimum temperature approaches varied from less than 1{sup 0}C for packing to 13{sup 0}C for the empty column. High heat transfer rates were obtained in all cases, however, columns should be sized on the basis of liquid and vapor traffic. The solubilities of hydrocarbons were determined for normal hexane, pentane and butane in water and sodium chloride and calcium chloride brines at various temperatures. The values seem to be internally consistent and salt content was found to depress hydrocabon solubility. Laboratory stripping tests showed that gas stripping can be used to remove hydrocarbon from reject hot water from the direct contact heat exchange column. Although the gas volumes required are small, stripping gas requirements cannot be accurately predicted without testing. A computer program was used to study the effect of operating variables on thermodynamic cycle efficiencies. Optimum efficiencies for the moderate brine conditions studied were obtained with isopentane as working fluid and relatively low …

A fusion-melt and dissolution assay method has been developed and tested for the quantitative analysis of high-fired plutonium dioxide. The method employs fusion of the plutonium dioxide at temperatures greater than the melting point of an eutectic mixture of potassium pyrosulfate plus sodium peroxide. The resultant melt is then titrated directly by either controlled potential coulometry or a gravimetric titration, using standardized ceric sulfate as the titrant. It has been concluded from these investigations that by using the techniques described, high-fired plutonium dioxide (stochiometric) can be quantitatively dissolved and assayed to a degree heretofore beyond the state-of-the-art, while showing direct traceability to the Federal standards. After fusion, the dissolution and direct assay is applicable to existing routine analytical procedures. The method was designed so as to minimize physical handling, simplify the chemical operations, and maximize the personal safety of the analyst at an appreciable cost savings per analysis. (auth)

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Experimental work in the area of the ambient-temperature, steady-state behavior of the lithium electrode was completed. The following conclusions were drawn: 100 percent coulombic efficiency may be approached over a wide range of concentrations, flow conditions, and current densities; coulombic efficiency is approximately equal to I/sub e//I/sub l/, and I/sub e/ is the current in the external circuit, and I/sub l/ is the diffusion-limited current. Li electrode resistivities of (0.4 to 1.0) x 10/sup -4/ ..cap omega..-m/sup 2/ were obtained, and thus the plane-parallel configuration is suitable for batteries of the lithium-water type. Work on the characterization of Li/I/sub 2/ and Li/Br/sub 2/ analog batteries was begun. (RWR)

Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80 percent. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59 percent and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high recirculating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable ($1000/kW(e)).