The neutral-beam injection systems for the next generation of U. S. fusion experiments (TFTR, MX, Doublet III) have requirements that considerably exceed the present state of development. TFTR, for example, desires 20 MW of 120-keV deuterium atoms in pulses of 0.5-sec duration. The neutral-beam systems needed to meet these demands will be large and complex and will require much development effort. In order to develop components for these new systems, a new, large test facility was constructed. The vacuum system, which has a volume in excess of 170,000 liters, will handle the pulsed gas loads by volume expansion; the gas will be pumped out in the one-minute intervals between pulses. The power-supply philosophy and specification are discussed in an accompanying paper. A mini-computer system will be used to monitor and control the power supplies and to diagnose the beam. Of the beam-line components, a plasma source and 120-kV accelerator structure which are under construction are discussed. A new long-pulse version of our 15-cm-diam high-current plasma source has been developed. Significant improvements have been made by re-orienting the filaments, so that they produce closed magnetic field lines near the wall, and by changing the shape and position of the anode. This …

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Four open cycle OTEC concepts are described. These are: (1) single, vertical-axis turbine; (2) multiple, horizontal-axis turbines; (3) foam lift/hydraulic turbine; and (4) mist lift/hydraulic turbine. A preliminary assessment of achievable performance is made in addition to a description of the subsystem performance objectives which would support the achievement of the full potential inherent in these concepts. The results and conclusions of the paper include a description of the research objectives, achievement of which make open cycle OTEC a viable alternative as a nationl energy source.

This paper extends the procedure to analyse the heterogeneous FBR spectra with depletion.

Gamma-ray spectroscopy is used to assay plutonium solutions flowing through thin sample cells. The direct measurement of gamma-ray intensities are used to determine the plutonium isotopic content and total concentration. The development of spectral analysis algorithms, the use of appropriate instrument internal standards, techniques to minimize spectral acquisition times, and methods to deduce the /sup 242/Pu content are discussed. Results of experiments on plutonium solutions in the 200 to 500 grams/liter concentration range of typical light water reactor isotopic content are given. These solutions typify the purified plutonium product streams in a reprocessing plant. The isotopic and total plutonium assay results as determined by this technique are within 0.5% of the reference values, as determined by mass spectrometry and controlled potential coulometry, respectively. Similar techniquescan also be applied to low concentration plutonium solutions. Plutonium isotopic ratios can be determined by this technique and the alpha specific activities computed. For low concentration (10/sup -0/ to 10/sup -4/ grams/liter) streams, cerium activated Vycor scintillation detectors can then be used for plutonium monitoring. This is compared with other proposed methods of on-line plutonium analyses. Modes of operation of these monitors for real-time inventory and diversion detection are discussed.

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In summary, analyses have been obtained for approximately 60 elements for sized flyash particles from two coal-fired steam plants. Evaluation of data from the elemental analyses, including the concentration dependence upon particle size, electron microscopy, ESCA, and mass spectrometry suggests a mechanism for formation of the submicron particles in some coal-fired plants. This mechanism involves bursting of larger particles during gas expansion and production of a very large number of very small particles which ultimately form particles in the 0.1 ..mu..m to 1.0 ..mu..m size range by coagulation. The condensation of volatilized material would then proceed concurrently with the bursting and coagulation process. The factors which determine the volatility of trace elements during coal combustion have been examined. While the organic affinities of individual trace elements in coal are likely to play a role, we have been unable to obtain clear verification of this point in initial studies.

In accord with recent custom, the organizing committee for this conference has scheduled this review paper on beam instabilities. In view of the various review papers which already exist and the fact that the fundamentals of the subject have even been treated in a textbook, I thought this paper might best be devoted to a limited part of the rather large field of beam instabilities. Thus, I have selected only an aspect of the general subject, but an aspect which has during the last years been very much at the center of activity, and will--if my judgment is correct--be even more so in the years to come. I wish to concentrate, here, on the interaction of a relativistic particle beam with itself which is a result of the coupling of the beam with its surroundings. Before approaching this topic, a few remarks on the existing review papers are in order. A comprehensive treatment of beam instabilities may be found in Ref. 1, where, also, the reader will find some 48 references to the original literature. In Refs. 2 and 3, the General subject is approached from other points of view. Reference 4 is concerned with some special topics, but treats …

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The Brookhaven National Laboratory Archive and Dissemination System (BNLADS) is designed to deal with the record keeping associated with archiving and disseminating sequential files through a computer network. This data base management system (DBMS) is implemented in a host language that is a subset of PL/I. The stored sequential files that can be dealt with by the BNLADS must be in character mode (ASCII, BCD, EBCDIC). The accessing of fields is specified by a format description which allows for forward processing of fields only. The structure of a case type statement allows for a data field determining a format sequence from a set of format sequences. A data description language (DDL) was devised to describe the accessing sequence of stored sequential files. A data model definition gives the user a view of the content of each stored sequential file. The DDL requires all field type references to contain the field name, so that the BNLADS can access all stored sequential files by logical field name and can write stored sequential files by stating the logical field name without the necessity of referring to formats. The BNLADS is architected in a stratified form in which the application programs are built on …

An important objective of the light water reactor pressure vessel (LWRPV) surveillance dosimetry program is to validate and calibrate dosimetry and damage analysis techniques as well as to guide required neutron field calculations that are used to correlate changes in material properties with characteristics of the neutron irradiation field. As part of this activity, the Hanford Engineering Development Laboratory (HEDL) performed neutron flux calculations in a model of the light water test reactor of the Nuclear Science and Technology Facility of the State University of New York at Buffalo. The purpose of these calculations was to provide a consistent analysis base for projecting radiation damage produced by one reactor facility to that which would be incurred in another reactor facility.

Displacement damage by 15 MeV (d-Be source) and fission neutrons at 30$sup 0$C in high purity niobium single crystals has been studied by transmission electron microscopy. The fluence of the 15 MeV neutrons was 1.5-- 2.0 x 10$sup 17$ n/cm$sup 2$ and the fluence of the fission neutrons (5 x 10$sup 17$ n/cm$sup 2$) was chosen so that samples from both types of irradiations had approximately the same damage energy. In both 15 MeV and fission neutron irradiated specimens, the loops were observed to be about $sup 2$/$sub 3$ interstitial and $sup 1$/$sub 3$ vacancy type. The analysis of Burgers vectors of the dislocation loops showed that more than $sup 2$/$sub 3$ of the loops were perfect a/2(111) and that the rest were a/2(110) faulted. It is concluded that at equal damage energies, the detailed nature of the damage is the same for 15 MeV and fission neutron irradiated niobium. (auth)

Nuclear wastes which are logical candidates for deep geologic disposal include commercial (spent fuel, reprocessing) and defense wastes. It is expected that the 5250 metric tons of spent fuel discharged through the end of 1978 would increase to about 100,000 tons by the end of 2000. The individual characteristics of each waste type (spent fuel, solidified waste, defense wastes) are described in turn. (DLC)

The use of achromat concept (1) to facilitate chromatic corrections in large storage rings is illustrated. The example given in this report is a lattice for a 75 GeV/c ring with six interaction regions having a beta x = 1.6 m, a beta y = 0.1 m and a luminosity of 1.4 10/sup 32/ cm/sup -2/s/sup -1/. The chromatic corrections are done with four families of sextupoles, two for each transverse plane, the strengths of which are determined by the solution of four linear equations in four unknowns. The basic simplicity of the method allows on-line control of the sextupole adjustments.

A comprehensive experiment to study drift from mechanical draft cooling towers was conducted. The data from this study are to be used for drift deposition model validation. Results show the effects of tower geometry and orientation with respect to the wind and to single or two tower operation. The effect of relative humidity on droplet evaporation as a function of downwind distance can also be seen.

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Reflection of 50 eV to 10 keV H atoms from polycrystalline Cu, Nb and Au targets has been calculated using the binary collision cascade program MARLOWE. The fractions of particles and energy reflected (backscattered) increase with increasing atomic number of the target and decrease with increasing incident energy. The results indicate that the effects of polycrystallinity are modest, reducing the amorphous reflection coefficients by about 25 percent. The calculations agree quite well with the experimental data for Cu and Au, but are about a factor of two larger than is observed for Nb.

The desire to use TMS 9900 devices in several small control and data acquisition applications without paying for a development system to do it led to the development of several simple, effective techniques for doing TMS 9900 programing and debugging on a TI 980 system. The 980 assembler lends itself easily to the redefinition of operation codes required to assemble programs for the 9900. Also, a simple interconnection between the 980 and the 9900 allows operation of the 9900 and monitoring of the operation of the 980. Finally, special operation codes were developed within the 980 assembler which allow programing of hardware control on the 9900 system via a macro-language tailored to a particular 9900 hardware configuration. 4 figures.

A serious problem in the development of geothermal energy is the availability of durable and economical materials of construction for handling hot brine and steam. Hot brine and other aerated geothermal fluids are highly corrosive and they attack most conventional materials of construction. Brookhaven National Laboratory has been investigating the use of concrete polymer materials as alternate materials of construction for geothermal processes. To date, successful field tests have been demonstrated at the Geysers, US Bureau of Mines Corrosion Facility, and at the East Mesa Geothermal Facility. This is a survey of field and laboratory evaluations of concrete polymer materials which have been shown to be durable and economical as alternate materials of construction.

A brief history of Decontamination and Decommissioning (D and D) experience at the Idaho National Engineering Laboratory is presented as an introduction to the status of current projects. Details are then presented as an introduction to the status of current projects. Details are then presented on a project to remove sodium from some major components of the Hallam reactor and on the Organic Moderated Reactor Experiment (OMRE) decommissioning project. Cost, schedule, waste volume, and other technical data from these projects are presented. In addition, a brief summary of the future INEL D and D program is presented.

Core restraint systems in LMFBRs maintain control of core mechanics and configuration behavior. Core restraint design is complex due to the close spacing between adjacent components, flux and temperature gradients, and irradiation-induced material property effects. Since the core assemblies interact with each other and transmit loads directly to the core restraint structural members, the core assemblies themselves are an integral part of the core restraint system. This paper presents an assessment of several advanced core restraint system and core assembly concepts relative to the expected performance of currently accepted designs. A recommended order for the development of the advanced concepts is also presented.

Corrosion of uranium in O/sub 2/ or H/sub 2/O atmospheres can be inhibited by first oxidizing the surface and then exposing it to organic vapors at temperatures near 400/sup 0/C. There is evidence that a polymeric material is formed on the surface and that it may be responsible for the corrosion inhibition. Polymer coatings can also be prepared using an RF discharge. This paper describes experiments in which uranium surfaces were exposed to an RF discharge and then evaluated as to their corrosion resistance and surface characteristics. Various plasma gases were used and in each case corrosion inhibition resulted. Samples for corrosion tests and ESCA/Auger examinations were prepared at the same time. The ESCA spectra reveal the formation of hydroxyl groups on uranium surfaces exposed to the RF discharges. Comparisons with corrosion tests suggest that a low surface hydroxyl concentration is associated with a low corrosion rate. The experiments reveal variations in both surface composition and corrosion reactivity which are related to the plasma gas used. These results are discussed in terms of possible reactions occurring between uranium and the RF plasma.

A simulation of a theta-pinch fusion power plant has been completed to the point where economic feasibility can be examined. A PL/I cost subprogram is presented for interfacing with the computer code TPFPP. This code is then used to obtain a first approximation of the costs for the reactor. Independent geometrical and plant design parameters are varied over a wide range, with simultaneous variation of magnetic field, minor first wall radius, and plasma maximum compression. The study indicates that the plant energy balance must be favorable, availability must be high, and major component costs must be low to achieve economical results. Although costing uncertainties remain, it is clear that development of easy and rapid replacement methods for reactor components is essential and that new staging concepts to reduce the implosion energy requirement must be pursued.

Separate abstracts have been entered into the data base for each included paper. (MOW)