Research progress is reported on the following topics: (1) conversion of 2, 4, 6-trichloroaniline to 2, 4, 6-trichloronitrobenzene; (2) nitration of 1, 2, 4-trichlorobenzene; (3) exploration of the route to 1, 3, 5-trichlorobenzene via aniline; and (4) direct nitration of trichloroaniline. (TFD)

Current activities include providing CRBRP design information based on tests of the IVHM Inflatable Seal to CRBRP conditions, testing the CRBRP dip seal configuration to determine its performance characteristics, and delineating the effects of sodium and radiation environments on the efficiencies of various seal materials.

Physician acceptance of computer-enhanced radionuclide scan results, presented in the form of small Polaroid pictures, has been very limited for a number of subjective reasons. A new recorder was designed and constructed that presents the results of computer augmented scans through a medium that is quite familiar to doctors, the standard 14 in. x 17 in. x-ray film. (auth)

The 10-cm (grid diameter) duoPIGatron ion source produces pulsed hydrogen ion beams of 10 to 15 A beam current in the 20- to 40-keV energy range for a duration of a few tenths of a second. To fulfill the requirements of the next generation of high-power neutral beam injectors for heating plasmas in CTR devices, this source has been enlarged to a version 15-cm in grid diameter. In addition, by utilizing a magnetic multipole line cusp field confinement method, the plasma created is characterized over the 15 cm grid diameter by a noise level within +- 10 percent and spatial density variations within +- 15 percent at a density on the order of 10/sup 12/ cm/sup -3/. This larger source has operated reliably and produced a beam current exceeding 30 A of hydrogen at 27 keV. Initial operation of a 20-cm version of this source employing line cusp confinement has produced an extraction current of 60 A at 33 keV.

Of the various possible unconventional natural gas resources that have been examined, the most recent, and by far the largest, is that which is dissolved in the hot salt water within the geopressurized zones of the Gulf Coast. Recent assessments have estimated that the amount of gas contained in these waters, underlying about 150,000 sq. mi. of Texas and Louisiana--both onshore and offshore--is between 60,000 and 100,000 quads. In addition to the natural gas, there is a huge potential for producing electric power from the heat content of the fluid, as well as other potential uses for hot water. The net value of this geothermal heat may be about half that of the natural gas. The major problems associated with commercial production of the fluids from these zones and the extraction of energy from the heat and pressure of the fluid are discussed and the long-term potential is estimated. It appears likely that commercial production will depend upon the existence of uncontrolled prices for natural gas and the satisfactory resolution of various legal, environmental, and institutional problems, all of which are likely to require considerable effort. Although the production potential from the Gulf Coast zones might be accurately estimated after …

A Faraday cup design for a 1 mA.cm/sup -2/ 100-keV, light-ion-beam measurement in background plasma is proposed. Features of this shielded, three-grid structure with deep target are described, and a mechanical draft is included. In the appendix, we reference and survey results of experiments reporting the number and energy range of secondary electrons and back-scattered ions originating on various metal surfaces bombarded with approximately 100-keV hydrogen and deuterium ions. Choice of target and grid materials in cup assembly follow from this survey.

Several practical motivations exist for the development of beam direct conversion systems that are compatible with the injection systems of large experiments such as the Tokamak Fusion Test Reactor (TFTR). We present a preliminary design in which we analyze the most acute problems involved in scaling up existing designs and apparatus to fulfill TFTR requirements. Some of the questions addressed are the requirements for electron suppression, gas pumping, compactness, and power densities. A new idea is presented that allows for the handling of higher beam power. The gross savings in the capital cost of injector power supplies for the TFTR will be about $7.2 million, but the net savings will be somewhat less than this. This preliminary design has not yet revealed fundamental limitations with respect to the development of beam energy-recovery systems operating at high levels of current, voltage, and power densities.

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 …

A P/sub 3/, 218 neutron group cross-section library in the AMPX master interface format has been generated from ENDF/B-IV data for 65 nuclides of primary interest in criticality safety calculations. The library was generated with the AMPX modular code system. Procedures used to generate the cross sections and the organization of the library are described.

The faciliies described will provide a direct route from the 241-S-151 and 241-U-151 Diversion Boxes to the 241-SY Tanks. The 244-S Catch Station will consist of a 20,000 gallon primary tank contained within a concrete vault lined with carbon steel. Encased three-inch carbon steel process lines will be extended to the catch station pump pit from the 241-SY Tank Farm, the 241-S-151 Diversion Box and the 241-U-151 Diversion Box encasement. The facility will have its own ventilation system for exhausting the primary tank and the annulus area. A small instrument shack will house locally mounted instrumentation and controls. Existing designs for Project B-103 will be used where similarities exist (H-2-38200). The project is expected to cost $1,900,000 and require 19 months for the initiation of Title I design until construction is complete.

An rf system is described for the 500-MHz cylindrical resonator that is coupled to the Astron beam to modulate its energy by +- 1.5 percent.

This report describes the RTG degradation mechanisms which have been identified as occurring in thermoelectric power generating systems that use the alloy of silicon germanium as the thermoelectric material and that incorporate a multifoil thermal insulation system. The synergetic effects of all of the identified degradation mechanisms are determined by a computer code, DEGRA, which calculates the available generator output power as a function of generator operating time.

Collections of abstracts of papers published during the previous calendar year in the areas of high energy physics, nuclear sciences, materials science and molecular sciences are presented.

The second Personnel Dosimeter Intercomparison Study (PDIS) was conducted at Oak Ridge National Laboratory's DOSAR Facility during the period February 18-19, 1976. Eleven independent organizations participated in an intercomparison of neutron and gamma-ray dosimeters used for routine personnel dosimetry. The dosimeters, which were shipped to the DOSAR Facility, were exposed at the Health Physics Research Reactor to one of three ''standardized'' radiation fields which have been used for the past several years for intercomparing nuclear accident dosimeters. The results of PDIS reveal that estimates of dose equivalent vary over a wide range. For a given radiation field these dose estimates may vary by more than a factor of 2, indicating the need for continued evaluation of the response of personnel dosimeters used in mixed fields of neutron and gamma radiation.

This report describes the incorporation of input--output technical coefficients for five new energy supply and conversion technologies as estimated by the MITRE Corporation into a 110-sector Energy I--O Model. The five new technologies are solvent refining of coal, oil shale mining and retorting, high-temperature gas-cooled reactor electricity generation, high-BTU coal gasification, and COGAS combined-cycle electricity generation. Incorporation of seven existing energy supply and conversion technologies is also described: crude oil and gas extraction, coal mining, refined petroleum products, pipeline gas, fossil electric generation, and hydroelectric generation. Non-energy input coefficients are given in units of 1967 $/10/sup 6/ BTU and represent the inputs in constant 1967 dollars from non-energy sectors (e.g. manufacturing, transportation, services) required per 10/sup 6/ BTU of energy production by each of these energy supply technologies. The 90 non-energy sectors included are based on the Bureau of Economic Analysis 83 sector input--output structure for 1967 with minor disaggregations. Energy input coefficients are given in units of BTU/BTU.

In a study of three 2D radiative transfer methods, equilibrium diffusion, nonequilibrium diffusion, and S/sub n/, as applied to the interaction of the reflected shock with a fireball near the surface, the following results were obtained. The equilibrium diffusion method requires modifications to transfer energy through optically thin zones. The present S/sub n/ method, as included in YAQUI-SN, i.e., the TWOTRAN code, has troubles in the treatment of a thick/thin interface. Improvements are possible using methods developed by I. Grant (J. Comput. Phys., v. 2, no. 4, 381-402(June 1968)) or D. Barfield (ibid., v. 10, no. 3, 420-431(Dec. 1972)). The nonequilibrium diffusion or moments method appears to be the most useful since it will limit properly in the optically thick and thin regions, but methods to determine the variable Eddington factors have not been successfully developed as yet. 7 figures.

This paper reports results of 2XIIB neutral-beam injection experiments with plasma-stream stabilization. The plasma stream is provided either by a pulsed plasma generator located on the field lines outside the plasma region or by ionization of neutral gas introduced at the mirror throat. In the latter case, the gas is ionized by the normal particle flux through the magnetic mirror. A method of plasma startup and sustenance in a steady-state magnetic field is reported in which the plasma stream from the pulsed plasma generator serves as the initial target for the neutral beams. After an energetic plasma of sufficient density is established, the plasma generator stream is replaced by the gas-fed stream. Lifetimes of the stabilized plasma increase with plasma temperature in agreement with the plasma stabilization of the drift-cyclotron loss-cone mode. The following plasma parameters are attained using the pulsed plasma generator for stabilization: n approximately 5 x 10/sup 13/ cm/sup -3/, anti W/sub i/ approximately 13 keV, T/sub e/ = 140 eV, and ntau/sub p/ approximately 7 x 10/sup 10/ cm/sup -3/.s. With the gas feed, the mean deuterium ion energy is 9 keV and the peak density n approximately 10/sup 14/ cm/sup -3/. In the latter case, …

Two billets were pressed from each of three lots of 90503 mock. One billet from each of these lots was pressed using dried powder. Samples were taken from each pressing charge just prior to pressing and volatile content measured. Each of these six billets were then machined into compression and tensile specimens. Additional compression specimens were machined from an existing hemispherical part made from one of these lots of material. Dimensional stability tests were conducted on parts from each billet and the hemisphere. Compression and tensile testing was conducted at 21 C and 49 C on specimens from each of the six billets. The small scale compression specimens from the hemisphere were also tested at these temperatures. The mechanical properties testing shows that the compression strain at rupture and the tensile rupture stress were significantly affected by the higher temperature. No apparent differences were seen between parts made from dried or normal powder.

The coreless Hartree--Fock effective potential (CHFEP) method is used to replace the core orbitals for atoms of the first three rows of the periodic table. Self-consistent field (SCF) calculations indicate that these effective potentials give Hartree--Fock quality orbitals and orbital energies. Optimized small basis sets for use with these effective potentials are presented along with some tests of these basis sets. It is seen that the effective potential allows one to use such small basis sets without the introduction of any serious error. These smaller basis set calculations allow for great savings in computational time and cost. (auth)

The calculations reveal that the H + H/sub 2/O and H + HF exchange reactions are both characterized by a large energy barrier (on the order of 20 to 30 kcal/mole) and a transition state possessing significant Rydberg 3s character on the central atom. The presence of high energy barriers means that both exchange reactions will be extremely slow except at very high temperatures.

ABCXYZ is a computer code for obtaining the Cartesian components of the vector potential and the magnetic field on an observed grid from an arrangement of current-carrying wires. Arbitrary combinations of straight line segments, arcs, and loops are allowed in the specification of the currents. Arbitrary positions and orientations of the current-carrying elements are also allowed. Specification of the wire diameter permits the computation of well-defined fields, even in the interiors of the conductors. An optical feature generates magnetic field lines. Extensive graphical and printed output is available to the user including contour, grid-line, and field-line plots. 12 figures, 1 table.

This report is intended to be a "user manual" for the Lawrence Livermore Laboratory version of the Eulerian incompressible hydrodynamic computer code ABMAC. The theory of the numerical model is discussed in general terms. The format for data input and data printout is described in detail. A listing and flow chart of the computer code are provided.

Differential cross sections for the reaction /sup 3/H(d,n)/sup 4/He have been measured at 7.00 and 10.00 MeV using the time-of-flight technique. By measuring both /sup 3/H(d,n)/sup 4/He and /sup 2/H(t,n)/sup 4/He at the same center of mass, energy-complete distributions between 0/sup 0/ and 180/sup 0/ have been obtained. The absolute scales have been established within +- 1.5 percent by using the accurate /sup 2/H(t,/sup 4/He)n cross sections at 20.0 MeV as a standard.

The parametric decay of an electromagnetic wave into two electron plasma waves is considered. The electromagnetic wave is obliquely incident on the density gradient. The resulting analysis shows that the threshold for absolute instability decreases as the angle of incidence of the electromagnetic wave relative to the density gradient approaches 90/sup 0/. The importance of this result to laser fusion is discussed.