Essential tools are provided for a program of rewriting field theories in terms of particle-string variables. The general methods are illustrated in the case of quantum chromodynamics: (1) One finds the particle-trajectoy representation for the quark Green's functional. (2) One derives directly correct end-point terms for quarks at the ends of strings. (1) and (2) are for any number of dimensions. (3) In two dimensions, one finds a functional bridge from quantum chromodynamics to the Bardeen-Bars-Hanson-Peccei string.

At Hanford, strontium-90 is removed from high-level nuclear fuel reprocessing waste and converted to strontium-90 fluoride. This /sup 90/SrF/sub 2/ is doubly encapsulated in high-integrity containers which are placed under water in monitored storage pools. Conversion of /sup 90/SrF/sub 2/ to a more immobile compound may be necessary and/or desirable as part of the overall plan for the long-term management of Hanford Defense Wastes. Glasses containing up to 40 mass percent SrF/sub 2/ and having leach rates in the range 1 x 10/sup -8/ to 1 x 10/sup -5/ gram Sr/(m/sup 2/ . s) (1 x 10/sup -7/ to 1 x 10/sup -4/ g Sr/cm/sup 2/ . day)) have now been prepared. From 0.2 to 5 percent of the fluorine is volatilized during the melting of the glass batch at temperatures up to 1500/sup 0/K. At present, the heat generation limit for commercial glasses stored at a nuclear waste repository is 5 kW per canister. All glasses described here would exceed that limit by more than a factor of five. The stored /sup 90/SrF/sub 2/ may be treated separately from the bulk of Hanford waste, in which case it would be diluted to an acceptable power level with inert chemicals …

CALOR is a Monte Carlo program package, written in FORTRAN IV, that is designed to assist experimentalists in evaluating and analyzing different types of calorimeter systems that are used in many high-energy physics experiments to determine the energy and direction of incident hadrons, leptons, and photons. This code package is intended to be used with the code package HETC, which supplies needed information on the transport of hadrons and on the spatial location of the electromagnetic source energy. Input and output for a sample problem are presented. 3 figures, 1 table.

Compressive creep tests were performed on molybenum samples exposed to four different pre-test conditions: (1) annealed; (2) annealed and neutron irradiated at 480/sup 0/C to a fluence of 5 x 10/sup 19/ n cm/sup -2/ (E > 1 MeV); (3) stress-relieved; and (4) stress-relieved and neutron irradiated at reactor ambient temperature to a fluence of 1 x 10/sup 19/ n cm/sup -2/ (E > 1 MeV). The tests were performed in the temperature range of 600 to 900/sup 0/C with an initial applied stress of 176.5 MPa. Both pre- and post-test specimens were examined using electron microscopy and the relationship between substructure and mechanical properties is discussed. Possible controlling mechanisms of deformation are proposed and activation energies for creep are determined.

The fluxes of protons emitted during solar flares since 1956 were evaluated. The depth-versus-activity profiles of /sup 56/Co in several lunar rocks are consistent with the solar-proton fluxes detected by experiments on several satellites. Only about 20% of the solar-proton-induced activities of /sup 22/Na and /sup 55/Fe in lunar rocks from early Apollo missions were produced by protons emitted from the sun during solar cycle 20 (1965--1975). The depth-versus-activity data for these radionuclides in several lunar rocks were used to determine the fluxes of protons during solar cycle 19 (1954--1964). The average proton fluxes for cycle 19 are about five times those for both the last million years and for cycle 20. These solar-proton flux variations correlate with changes in sunspot activity.

A simple method for estimating the solubility of TATB in various solvents is presented. We consider it unlikely that a solvent will be found in which TATB is more soluble than 0.1 percent (w/v). Exceptions are the so-called superacids in which the solubility of TATB exceeds 20 percent (w/v).

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Some of the features of the computer program GEOTHM are shown. This program designs and optimizes thermodynamic process cycles. Several examples of geothermal cycle optimization are given. Three dimensional plots generated by the computer show how the optimization process works.

Activities included the preparation of presentations for the NRC review committee. Also, a draft program plan on the Protection of Nuclear Materials for both fixed facilities and in-transit systems was submitted to the NRC. Other activities have focused primarily on the development of evaluation methodologies. These efforts have included the development of a computer graphics implementation of EASI (Estimate of Adversary Sequence Interruption), engagement model developments, ISEM (Insider Safeguards Effectiveness Model) documentation, pathing algorithm improvements, and facility characterization methodology improvements. A large effort has been expended in defining and interfacing with possible contractual support involvements. Areas of these involvements include a generic safeguards data base, fault tree analysis techniques, physical protection modeling, human attribute definitions, neutralization modeling, and safeguards network symbology models.

The LLL developed electronic pressure meter (EPMT) is a portable static-pressure calibration instrument for use with the LLL telemetry transducer system at the Nevada Test Site (NTS). It is significantly more accurate and rugged than the bourdon-tube pressure gauge it replaces, and can be incorporated into a field-use, semi-automatic, pressure calibration system. The process by which a transducer is selected for EPMT use from the inventory of field-service-certified transducers and subjected to an extensive preconditioning and calibration procedure is described. By combining this unusual calibration procedure with a unique, statistically based data-reduction routine, the total uncertainty of the measuring process at each calibration point can be determined with high accuracy.

A recent proposal for reducing the end loss of a linear theta pinch is to produce moving magnetic mirrors at the coil ends. The concept entails the sequential pulsing of an axially arranged series of two-turn coaxial coils. The electrical design of such a system presents some unique problems. Ideally, the individual pulse circuits should be completely independent. This would facilitate the design by eliminating interactive effects. In practice, the circuits must be interconnected through isolating inductors to enable the production of a uniform biasing magnetic field. Moreover, the coils must be located physically close together. This produces strong magnetic coupling between the pulse circuits, which can seriously affect the shape and speed of the inward-moving magnetic-mirror field. Possible systems were modeled for the NET-2 circuit analysis code. The models took account of the inductive coupling between the individual circuits in the model. The results show that an increasing magnetic mirror can be produced provided the radius of the theta pinch is not too great compared to the intercoil spacing. The peristaltic field can be maintained for several cycles in the inner coils. The voltage hold-off requirements on the pulse circuit switches are found to be severe, but not impossible …

A draft Manual of Recommended Practice for Aerosol Sampling and Evaluation was completed and sent to the Energy Research and Development Administration (ERDA) Division of Safety, Standards, and Compliance (DSSC) for review. The results of the Survey of Sampling Techniques for Defining Respirable Concentration and/or Particle Size Characteristics of Aerosols were published as LA-6087. The need for greater standardization of ERDA aerosol sampling techniques was indicated. The Aerosol Training Course was presented in 11 sessions to 85 persons. General elements of good practice were emphasized, and recommendation of specific sampling devices or procedures was avoided. A system for estimating dissolution rates of plutonium aerosols was developed. Studies indicate that plutonium aerosols found in the field have a rapid initial dissolution phase followed by a slower secondary phase. Three methods of particle sizing air samples collected on membrane filters were investigated. The most promising was a scanning electron microscope electron microprobe (SEM-EMp) method. An operating plutonium handling facility was a model for development of techniques to evaluate aerosol surveillance systems performance. Airborne contamination records were studied. The physicochemical properties of a plutonium aerosol existing in the facility were investigated in relation to plutonium handling operations. The techniques developed have indicated some …

ERDA and Marathon Oil Company contracted together for a commercial scale demonstration of enhanced oil recovery by the Maraflood (TM) oil recovery process. This M-1 Project is located within Sections 15, 16, 21 and 22, T6N, R13W, Crawford County, Illinois, encompassing approximately 407 acres of Robinson Sand reservoir developed in the first decade of the century. The area covers portions of several waterfloods developed on 10-acre spacing in the 1950's that were approaching their economic limit. This report describes all M-1 Project facilities, how they were prepared or constructed, their purpose and how they operate: (1) wells (drilling and completion); (2) production facility; (3) injection facility; and (4) various service systems required during project development and/or operation. (48 fig, 7 tables) (DLC).

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A wavelength tunable infrared laser heterodyne spectrometer was taken into the stratosphere as part of the instrumentation package on board the stratospheric scientific research balloon, STRATCOM VI, in order to obtain high-resolution atmospheric absorption spectra of nitric oxide and water vapor by measurement of the attenuation of the solar radiance at approximately 5.24 microns. This report describes the development of this instrument system and the experimentation that characterized its performance.

Spatially resolved profiles of low charge state carbon and aluminum ion impurity radiation from EBT were obtained in the vacuum ultraviolet. The data shows EBT to be remarkably free from impurities. Loss times in the surface plasma are found to be approximately 300 ..mu..sec. Thus about one fourth of the input power supports the surface plasma. The measurement places an upper limit on the C V density in the core plasma which indicates that the core plasma is shielded from the impurities in the surface plasma.

Routine reactor operation with only three end-of-cycle shutdowns this quarter resulted in an on-stream time of 96.5 percent. Total on-stream time for the year was 93.8 percent. Basic operating data for the quarter are listed.

Two specimens of a commercial version of the LLL model LC-13 laser calorimeter have been tested. A comparison of peak-reading and corrected-temperature-rise methods of treating the calorimeter response has also been performed.

A device that measures charge-exchange flux to determine the angular distribution of the 2XIIB plasma is described. Charge-exchange products heat circular nickel foils (placed at 15/sup 0/ intervals in theta and at constant radius on an arc parallel to the z-axis) and the voltage drop across the foils (produced by constant-current sources) provides a measure of the changes in resistivity. The charge-exchange flux at each foil is proportional to the plasma distribution at that angle. Use of this technique is limited by the resistivity and heat resistance of the circular nickel foils, but could conceivably be extended to other shapes and materials. The Hall-Simonen and ''time-average'' measurement of angular distribution are compared and the characteristic times of loss (gain) are calculated from theory. The g(..mu..) detector may be used to experimentally verify these times of loss (gain) and also to analyze plasma pressure stability. Current microwave measurements show that plasma has an exponential density dependence in z and assumes a flux tube rather than a p(B) density dependence. A distinct angular distribution (determinable by the detector) is associated with each of these dependencies. The codes to simulate injection and resulting angular distribution, charge-exchange capture, and heating and signal of the …

This manual describes the user interaction with the CIRMIS System. The portions of the system are divided into three sections: Well-based Data Retrieval System describes the procedures involved in the retrieval of well-based data. Capabilities are available to display graphically various types of information relating to wells and/or obtain hard copy plots and line printer listings of these data. Special Applications and Manipulations describes the procedures involved in the generation and manipulation of surface files, the generation and use of map boundary files, special computer models that utilize these data, and special utility programs. Model Input Sequencing describes the procedures involved in setting up of input parameters and control of Major Predictive Models controlled by the CIRMIS system. Due to the size of these models and the large amounts of data required, they are run on a PDP-11/45 computer with large mass storage capabilities Control of these programs is provided through the use of a smaller computer with visual interactive capabilities. 59 figures. (RWR)

The cumulative quantities of free standing water resulting from the solidification of simulated wastes with urea-formaldehyde (UF) and portland type II cement were determined. The effect of the waste/solidification agent ratio on the cumulative free standing water for selected wastes solidified with UF was found to be related to sample shrinkage. Urea-formaldehyde decontamination factors for free standing water were determined with /sup 137/Cs, /sup 85/Sr, /sup 60/Co, and /sup 59/Fe. With the exception of /sup 85/Sr for which UF was shown to have a decontamination factor of 1.6-1.9, the specific activity of the free standing water was essentially equal to that of the waste prior to solidification. The release of cesium from UF in distilled water was measured by a static leaching technique. The effect of the leachant renewal interval and the ratio of the leachant volume (V/sub L/) to the sample external geometric surface area (S) was examined. The proposed leachant renewal interval of once/day and V/sub L/S = 10cm was found to be satisfactory for leaching of these samples. Samples of a proprietary polymer agent developed by the Dow Chemical Company were tested to determine water loss with exposure to ambient air, weight loss with temperature (TGA), thermal …

The continuum ..gamma..-ray spectrum following neutron emission in a (HI,xn) reaction consists of a high-energy tail, the statistical cascade, and a lower-energy bump, the yrast cascade, which contains most of the intensity and consists mostly of stretched E2 transitions. Thus, a good approximation to the average angular momentum carried by the ..gamma..-rays is 2N/sub ..gamma../-bar. Under favourable conditions, effective moments of inertia can be deduced for states up to the top of the ..gamma..-ray cascade. The maximum angular momentum in the cascades is probably limited by ..cap alpha..-emission for nuclei with A < 150 and by fission for those with A > 150. 17 figures.

This paper presents some novel interpretations of fusion plasmas which may be of interest to both fission and fusion scientists and engineers. A new fusion ignition parameter (Tn/sub e/tau/sub E/)/sub I/ is proposed which is proportional to ..beta../sup 2/B/sup 4/ and inversely proportional to the fusion power density (P/sub Fusion/) of a reacting plasma. Curves are given for many potential nuclear fusion fuels. The energy utilization factor in existing devices is defined as f = P/ sub Fusion//P/sub Loss/ = (Tn/sub e/tau/sub L/)/(Tn/sub e/tau/sub E/)/sub I/; in experimental plasmas, f has increased by about two orders of magnitude in the past decade and now exceeds 10/sup -4/ (a &#x27;&#x27;nearest&#x27;&#x27; f* exceeds 10/sup -3/). The f factor is also analogous to its fission counterpart in the four-factor neutron multiplication factor k = f eta epsilon p, where f is the neutron thermal utilization factor. Past, present, and future fusion experiments are discussed briefly in this context.

A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the amount of radioactive materials released from a model recycle uranium conversion and uranium hexafluoride (UF/sub 6/) production plant and to determine the radiological impact (dose commitment) of the released radioactive materials on the environment. This study is designed to assist the US NRC in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base case model plant is representative of a licensable UF/sub 6/ production plant and has an annual capacity of 1500 metric tons of uranium. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments is calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. The methodology used in estimating the costs …