This report contains the abstracts of papers presented at a workshop on polycyclic aromatic hydrocarbons (PAH) such as those produced by coal conversion technologies. Their often carcinogenic nature imposes the obligation of providing adequate protection and measurement devices for workers and for the general public. The primary questions are as follows: What should be measured. Where and how should it be measured. What are the maximum permissible concentrations. This workshop and future workshops are intended to bring these problems into better focus and to help establish a consensus on what needs to be done in order to provide a dosimetry effort that will ensure the adequate protection of personnel. There were 32 attendees of this one-day meeting. The papers and discussions included current industrial hygiene practices, the development of government agency guidelines for worker protection, and a wide range of analytical techniques for PAH detection, some of which are still in the research stage and are unproven. The workshop was held at ORNL on February 26, 1976.

A mechanism that explains several of the observations of fragmentation of hot molten drops in coolants is presented. The mechanism relates the fragmentation to the development of acoustic cavitation and subsequent bubble growth within the molten material. The cavitation is assumed due to the severe pressure excursions calculated within the hot material as a result of the pressure pulses accompanying coolant vaporization at the sphere surface. The growth of the cavitation vapor nuclei inside the hot drop is shown to be influenced by the subsequent long duration surface pressure pulses. The variation of the amplitude of these surface pulses with experimental variables is shown to exhibit the same trends with these variables as does the variation in extent of fragmentation.

Newsletter issued by the Advisory Council for Technical-Vocational Education in Texas discussing news, events, and other relevant information related to technical and vocational education for adults in Texas.

Monte Carlo calculations were made to analyze the results of an integral experiment with an iron sample to determine the adequacy of neutron scattering cross section data for iron. The experimental results analyzed included energy-dependent NE-213 detector count rates at a scattering angle of 90 deg and pulse-height spectra for scattered neutrons produced in an iron ring pulsed with a 1- to 20-MeV neutron source. The pulse-height data were unfolded to generate secondary neutron spectra at 90 deg as a function of incident neutron energy. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV cross sections were made to analyze all reported results. Discrepancies between calculated and measured responses were found for inelastic scattering reactions in the range from 1 to 4 MeV. These results were related to deficiencies in ENDF/B-IV iron cross section data.

Analysis of the hypothetical upper limit accident in the Savannah River Test Pile showed that the offsite thyroid dose from fission product release would be <2.2 x 10/sup -3/ of the 10-CFR-100 guideline dose for 95 percent of measured meteorological conditions. Offsite whole body dose would be negligible. The Test Pile was modified to limit the length of test piece that can be charged to the pile. These modifications reduce the potential offsite dose to <2.2 x 10/sup -5/ of the regulatory guidelines. Assessment of Test Pile safety included calculations of transients initiated by a variety of reactivity additions that were either terminated or not terminated by safety systems. Reactivity addition mechanisms considered were abnormally driving control rods out of the pile and charging abnormal test pieces into the pile. The transients were evaluated in the adiabatic approximation in which three-dimensional calculations of static flux shapes and reactivity were superimposed on point reactor kinetics calculations. Negative reactivity feedback effects appropriate for the pile and the temperature dependence of material properties, such as specific heat and thermal conductivity, were included. The results show that, for the worst initiators, safety systems can prevent the temperature rise from exceeding 1/sup 0/C anywhere in …

The National Center for Analysis of Energy Systems at Brookhaven has been in operation since January 1976. This first annual highlights report outlines the scope of activities of the Center involving the integrated analyses of technological, economic, environmental, and social aspects of energy at the regional, national, and international levels. The objectives of the Center and major accomplishments of 1976 are described along with a list of active projects and publications. The energy data bases and analytical models used in the course of policy analyses are also described. The major ongoing activities of the Center include: long-range forecasting of energy-economic relationships; regional energy and environmental policy; comparative health effects of alternative energy systems; technology assessment and energy R and D priorities; development of energy-economic environmental models and data bases; R and D strategies for International Energy Agency; and energy technologies for developing countries.

Analytic solution for the envelope structures of two nonlinearly coupled lower hybrid waves propagating along their respective cone trajectories are obtained. The coupling occurs through induced scattering by particles. The results indicate anomalous spatial pump depletion may be important for present and future large scale tokamaks. Implications to plasma heating are also discussed.

The results of a survey of solar energy system applications of air conditioning are summarized. Techniques discussed are both solar powered (absorption cycle and the heat engine/ Rankine cycle) and solar related (heat pump). Brief descriptions of the physical implications of various air conditioning techniques, discussions of status, proposed technological improvements, methods of utilization and simulation models are presented, along with an extensive bibliography of related literature.

Included are the 14 papers presented by fusion researchers from ANL at the ANS meeting on controlled fusion. Abstracts for each paper are included. (MOW)

An overview is presented of the technical and economic feasibility for the development of a very high-temperature reactor (VHTR) and associated processes. A critical evaluation of VHTR technology for process temperatures of 1400 and 2000/sup 0/F is made. Additionally, an assessment of potential market impact is made to determine the commercial viability of the reactor system. It is concluded that VHTR process heat in the range of 1400 to 1500/sup 0/F is attainable with near-term technology. However, process heat in excess of 1600/sup 0/F would require considerably more materials development. The potential for the VHTR could include a major contribution to synthetic fuel, hydrogen, steel, and fertilizer production and to systems for transport and storage of high-temperature heat. A recommended development program including projected costs is presented.

This quarterly report is the second in a series intended to provide information on research and engineering activities being performed to improve the processing of irradiated reactor fuels, the production of plutonium, and the management of resultant chemical wastes.

This report includes several photographs and illustrations, as well as text, to describe a portable unit for filtering water samples. It "is preliminary and has not been edited or reviewed for conformity with Geological Survey standards and nomenclature."

The drift motions of trapped particles in a tokamak field with ripples lead to a new transport process in large tokamaks in addition to the diffusion process due to particles trapped in the ripples. We study this problem by solving the bounce averaged drift kinetic equation with a model collision operator. It is shown that the ''banana drift diffusion'' is proportional to the collision frequency when the poloidal banana drift frequency is smaller than the effective collision frequency. This result is contrary to earlier predictions. In a reactor regime, this loss mechanism is shown to be unimportant.

A collection of benchmark problems is used to test the finite-strain formulation of the LIFE-III fast-reactor fuel-element code. Analytical solutions for thick-wall cylinders loaded by internal and external pressure, valid for arbitrarily large strains, are presented for a linear viscous material. Similar problems are formulated for a nonlinear material, and numerical solutions are obtained using the Runge-Kutta method for the integration of an ordinary differential equation. These solutions are then compared with the corresponding solutions obtained using the LIFE-III code. With a proper choice of the number of spatial regions and time steps, good agreement is obtained between the two sets of solutions. The results indicate that the structural-analysis portion of the revised LIFE-III is valid for large strains.

In order to predict accurately the cost of producing methane from urban refuse, studies were initiated on the dewatering of the fermentor residue and the disposal of the residue from the system. Results of the research are reported under the following subject headings: fermentation system; rheological properties of reactor slurry; filterability of reactor effluent; residue dewatering--vacuum filtration; settleability of solids in the reactor effluent; settleability of sludges from centrate treatment; centrifugation of reactor effluent; leachate potential of dewatered reactor residue; calorific value of the reactor residue; residue incineration; the production of panelboards; caustic treatment of digester feed; and, treatment of filtrate--centrate. Appendixes A, B, D, and E are included; Appendix C, which includes computer programs and documentation, is bound separately as Volume II of this report. (JGB)

In order to predict accurately the cost of producing methane from urban refuse, studies were initiated on the dewatering of the fermentor residue and the disposal of the residue from the system. Experimental procedures and data are reported in Volume I of this series; related computer programs and documentation are reported in Appendix C, bound separately as Volume II. This appendix contains detailed information on the simulation model. It is divided into five major sections; logic flow and notes, simulation results, definition of major program variables, program listing, and sample output. The section on simulation results includes an analysis of the system under various operating conditions. The program was implemented on the University of Illinois DEC-10 system. (JGB)

Separate abstracts were prepared for the three sections of the report. (HLW)

The step-by-step procedure used to evaluate the performance of the air conditioning system in the Building 381 Hi Bay at the Lawrence Livermore Laboratory is described, and the results obtained at each step are discussed. From these tests it was concluded that: the 381 Hi Bay has a superior air conditioning system which is capable of +-/sup 1///sub 2//sup 0/F with five minute cycle periods with suitable electronic control and proper control probe location; thus far the system performance has been improved from +-3/sup 0/F and 25 minute cycles to +-1/sup 0/F and 10 minute cycle; there is an immediate need for continuous monitoring equipment and a regular maintenance and inspection cycle should be established to insure reliable temperature control; and electronic load control should be investigated. (LCL)

This report summarizes the initial effort of the Lawrence Livermore Laboratory involvement with the study of BWR Mark I pressure suppression pool dynamics. Analytical activity is described and calculational results are presented for several simplified geometries. Computer code authentication will be provided by a currently active program in benchmark tests. The experiment and some results are presented. A combined analytical and experimental program to evaluate air scaling hypotheses for hydrodynamic forces and pool motion is presented, along with some conclusions regarding model scaling.

A study was made of computer-simulated powder x-ray diffraction data for Ta/sub 22/W/sub 4/O/sub 67/, Ta/sub 2/WO/sub 8/, and Ta/sub 16/W/sub 18/O/sub 94/--the three compounds in the Ta/sub 2/O/sub 5/--WO/sub 3/ system from 27 to 69 mole percent WO/sub 3/. The crystal structures of Ta/sub 2/WO/sub 8/ and one form of Ta/sub 16/W/sub 18/O/sub 94/ (Type B) were deduced from reported data. 8 tables. (auth)

A neutron source designed for fusion-related radiation damage studies has been built based on the d + Be reaction. Using a 40 MeV, 20 ..mu..A deuteron beam from the Oak Ridge Isochronous Cyclotron neutron fluxes of 1 - 2 x 10/sup 12/n/cm/sup 2//sec are obtained over an area approx. 50 mm/sup 2/. The design of the source is described, together with time-of-flight and activation foil measurements of the thick target neutron yields from the /sup 9/Be(d,n) reaction for the angular range from 0 to 90/sup 0/. A dosimetry procedure based on these measurements is presented. In addition time-of-flight measurements of the thick target neutron yields for the Li(d,n) reaction are reported and compared with the /sup 9/Be(d,n) results.

Compositional data of coal liquid products derived from the H-Coal process were obtained. Two overhead products (one from the fuel oil mode of operation and the other from the syncrude mode of operation) were prepared by Hydrocarbon Research, Inc. from Illinois No. 6 coal. The compositional data of these products are tabulated, and characteristics of the materials are discussed. Separation and characterization methods, with slight modification, as developed by the Bureau of Mines-API Research Project 60 for characterizing heavy ends of petroleum, were successfully used in analyzing coal liquid distillates within the boiling range 200/sup 0/ to 540/sup 0/C. Distillates boiling below 200/sup 0/C were separated and analyzed using chromatographic and spectral techniques.

A seep approximately 50 meters east of trench 7 within the ORNL restricted area contains /sup 60/Co in concentrations of 10/sup 4/ to 10/sup 6/ dpm/g in the soil and 10/sup 3/ dpm/ml in the water. Traces of /sup 125/Sb and various transuranics have also been detected in the soil. However, because the volume of water discharge from the seep is small, the total radionuclide contribution from the trench 7 area to White Oak Creek and the Clinch River is insignificant. The /sup 60/Co is transported in the ground-water from the trench to the seep as organic complexes and is absorbed by manganese oxides and to a lesser extent by iron sesquioxides in the shale and soil. In the absence of these organic complexing agents, /sup 60/Co mobilization would be negligible because the sediment absorption capacity for inorganic forms of /sup 60/Co is extremely high. The primary objective of this study has been to investigate /sup 60/Co transport and absorption mechanisms as observed in the study area. Because the organic complexing characteristics of transition metals and transuranics are similar, the mechanisms of /sup 60/Co transport determined in this study may also apply to plutonium and other alpha-emitters. Also the experimental …

The chemistry of the CO/sub 2/--I/sub 2/--CH/sub 3/I--H/sub 2/O system in stainless steel has been investigated with respect to the probable reactions of these components in the KALC process. Iodine is stable in dry CO/sub 2/ contained in stainless steel; but in the presence of organic impurities or water, it is lost from solution via reactions which produce solid phases. Methyl iodide, however, is stable in either wet or dry CO/sub 2/ solutions. Distribution coefficients for I/sub 2/ and CH/sub 3/I between gas and liquid CO/sub 2/ have been measured from -26 to +30/sup 0/C; they show that the solutes favor the liquid phase as the temperature is lowered. The corrosion loss of I/sub 2/ in the presence of 10 to 200 ppm H/sub 2/O has been followed as a function of time at 0 and +21/sup 0/C. Weak associations between CO/sub 2/ and I/sub 2/, CO/sub 2/ and H/sub 2/O, and I/sub 2/ and I/sub 2/ can account for shifts in their respective distribution coefficients, but these associations are not strong enough to produce isolable phases. The occurrence of a weak CO/sub 2/.H/sub 2/O molecular species in the vapor is demonstrated by the near-infrared vibrations of the water group …