Progress on a program to develop commercially viable phosphoric acid fuel cell driven on-site integration energy systems is presented. A mass and energy balance was completed for one operating point of a selected power generation sub-system with a power output of 119 kW. Potentially, 87% of the LHV of the input fuel is available as bus bar electricity or useful heat. A 2 kW stack of conventional design and a 0.5 kW DIGAS cooled stack have been constructed and are on test at ERC. Renovation of a space for the Westinghouse stack test facility is underway and procurement of equipment has been initiated. The coupled cell temperature - current density analysis has been modified to include the effects of turbulent coolant flow and extended to permit analysis of up to 10 process plates between cooling plates. The REFORM computer program was verified by comparison with data received from the government project manager. A method for predicting carbon deposition was developed and compared with data from the literature.

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The code is primarily a manager of probabilistic data and deterministic mathematical models. The user determines the desired aggregation of the available models into a composite model of a physical system. MACRO1 then propagates the finite probability distributions of the inputs to the model to finite probability distributions over the outputs. MACRO1 has been applied to a sample analysis of a nuclear-waste repository, and its results compared satisfactorily with previously obtained Monte Carlo statistics.

The goal of this research was to convert the organics and sulfur in sulfite spent liquor (SSL) now classified as pollutants from sulfite pulp mills, into synthetic methane and protein by means of a combination chemical-biological process. Ozonization was used to break the high molecular weight lignosulfonate molecules present in SSL into lower weight fractions which could be metabolized by methane-producing bacteria and protein-producing yeast. Ozonization experiments showed that this treatment is effective in partially oxidizing and fragmenting lignosulfonates into fermentable substrates. This process is initiated at low ozone concentrations and proceeds rapidly until nearly 30% of the Chemical Oxygen Demand (COD) has been consumed. The conditions under which ozonization is conducted greatly affect the degree of oxidation and the molecular weight of the cleaved fragments. In spite of the appreciable oxidative cleavage of the lignosulfonate molecules, continuous-flow fermentation studies showed rather low yields of methane and yeast from ozonated SSL. Under optimum conditions, methane production averaged only 1.7 1/1 of SSL or approximately 3% of the total organics present. Protein production was somewhat more favorable with 6% of the organics being converted to yeast biomass. (6g/1). Neither fermentation fully used all of the oxygenated fragments produced by ozonization, and …

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)

A double-peak, energy-dependent Breit-Wigner model of the E1 gamma-ray strength function was applied to nuclei from As to Rh, to predict their neutron capture cross sections and capture gamma-ray spectra. A consistent set of model parameters was obtained in this mass region to describe the step in the low-energy tail of the E1 strength function. This step allows agreement with photonuclear data at high energies, the correct GAMMA/sub gamma/ to be obtained for agreement with neutron capture cross-section data, and the calculation of the observed hardness in the capture gamma-ray spectra. For nuclei at or near the closed, N = 50 shell, however, the double-peak assumption breaks down. In these cases, good results are still obtained if the same set of model parameters is applied, except that the E1 strength function is formulated in terms of the first, narrower peak. 8 figures.

A comparison of some features of the three tokamaks is given. The ORMAK and ISX-A have ceased operation. The ISX-B has completed a checkout phase with studies of circular, ohmically heated plasmas in which it performed much like ISX-A. Shaped and injection heated plasmas are being studied. Diagnostics for mode structures were the usual Mirnov loops for approx.B/sub theta/ and collimated soft x-ray detectors for the internal fluctuations approx.X. The approx.X measurements on ISX-A, and thus far on ISX-B, used only a single x-ray channel which veiwed vertically across the center of a minor cross section. Multiple channels were used on ORMAK in a fashion which permitted m number determinations at several plasma radii. For detailed studies, analog signals were stored on magnetic tape and later digitized for fast Fourier transform analysis.

Recent experiments on low-level irradiation during development raise questions relevant to ICRP Publication 26. Mice and monkeys were studied; the measured endpoint was the radiation-induced loss of female germ cells. Three issues are examined. The first is the numerical value of Q (quality factor) appropriate for low-energy beta rays. Comparisons of tritium with gamma radiation were made under conditions of chronic, low-level exposure, and the relative biological effectiveness (RBE) was found to approach 3. Its bearing on ICRP's recommendations concerning Q applicable to tritium is discussed. Second, female germ cells in squirrel monkeys before birth were discovered to be extraordinarily radiosensitive, more easily destroyed than those of mice. If this holds for other primates too, it has radiation-protection implications hitherto overlooked. Third, the contrast between massive germ-cell loss from chronic exposure in prenatal squirrel monkeys and reported radioresistance of oocytes to acute exposure in rhesus monkeys, unless due to species difference, suggests that during development protracted irradiation may be especially injurious. This also could have important radiation-protection implications and is under investigation. (ERB)

Actinides in ash can be leached effectively by refluxing with Ce(IV) in HNO/sub 3/; solubilization of actinide in ash was greater than or equal to 95% at ash concentrations to 30 g/l in stirred leachant. Plutonium and americium were the actinides present in the ash. Solubilized plutonium and americium were recovered from Ce(IV)-HNO/sub 3/ solution by solvent extraction. Extraction of plutonium into 30% tributyl phosphate in n-dodecane gave 99.99% recovery. The plutonium-depleted solution was then extracted with 30% dihexyl-N,N-diethylcarbamolylmethylenephosphonate (DHDECMP). Americium recovery was 99.64%. The Ce(IV)-HNO/sub 3/ system was compared with the HF-HNO/sub 3/ system now in common use. Advantages of the former included less equipment corrosion, no volatilization of silica, safe oxidation of carbon residues, minimal secondary waste (Ce is recycled), and better solubilization of actinide in the initial contact. However, additional contacts do not significantly improve solubilization, and a small fraction of actinide is not solubilized with Ce(IV)-HNO/sub 3/ that can be solubilized by HF-HNO/sub 3/. The effect of the fission product ruthenium on the dissolution of actinides in the Ce(IV)-HNO/sub 3/ system was investigated briefly, and a method for removing the ruthenium electrolytically was developed. Several process flowsheets were also considered. Actinide recovery requirements will suggest which …

The transfer of energy produced by the interaction of the intense pulses of short-ranged fusion microexplosion products with materials is one of the most difficult problems in inertially-confined fusion (ICF) reactor design. The short time and deposition distance for the energy results in local peak power densities on the order of 10/sup 18/ watts/m/sup 3/. High local power densities may cause change of state or spall in the reactor materials. This will limit the structure lifetimes for ICF reactors of economic physical sizes, increasing operating costs including structure replacement and radioactive waste management. Four basic first wall protection methods have evolved: a dry-wall, a wet-wall, a magnetically shielded wall, and a fluid wall. These approaches are distinguished by the way the reactor wall interfaces with fusion debris as well as the way the ambient cavity conditions modify the fusion energy forms and spectra at the first wall. Each of these approaches requires different heat transfer considerations.

Value Engineering, simply defined, is a systematic approach to getting more for your money. It has been used to reduce the cost of a wide variety of products by the D.O.D. and in principle, should be applicable to various phases of the Neutral Beam Program. With respect to R and D, the principles of Value Engineering must be used with caution. They are most effective in evaluating directed development with very specific goals, but can be misleading when considering advanced innovative work.

An investigation of the relative utility and performance of nine major household consumer products covered by the Energy Policy and Conservation Act is summarized. The objective was to define the terms utility and performance, to recommend methods for quantifying these two concepts, and to recommend an approach for dealing with utility and performance issues in the energy efficiency standards program. The definitions developed are: performance of a consumer product is the objective measure of how well, with the expected level of consumer input (following the manufacturer's instructions for installation and operation), the product does its intended job; and utility of a consumer product is a subjective measure, based on the consumer's perception, of the capability of the product to satisfy human needs. Quantification is based on test procedures and consumer survey methods which are largely already in use by industry. Utility and performance issues are important in product classification for prescribing energy efficiency standards. The recommended approach to utility and performance issues and classification is: prior to setting standards, evaluate utility and performance issues in the most quantitative way allowed by resources and schedules in order to develop classification guidelines. This approach requires no changes in existing Department of Energy …

A full description is given of a glow discharge deposition system, as well as a schematic. A growth rate of 2 to 3 A/sec is reported across a total substrate diameter of 76 mm, and films of a-Si:H free of oxygen and carbon contaminants have been obtained. Other films deposited include: doped and undoped a-Si:H and a-Si/sub x/C/sub 1-x/:H, n-i-p, a-Si:H plus n-i-p, a-Si:H plus a-Si/xub x/C/sub 1-x/. Optical transmission measurements from .35 to 50 microns wavelength were made on these films. A significant difference found in the vibrational spectra is the shift of the major stretching mode from 2000 cm/sup -1/ for a-Si:H to 2100 cm/sup -1/ for the a-SiC:H. A strong broad band centered at 1000 cm/sup -1/ appears when carbon is present. (LEW)

Maxwell-averaged reaction rates (sigma v-bar) are presented for 24 interactions between /sup 1/H, /sup 2/H, /sup 3/H, /sup 3/He, /sup 4/He, /sup 6/Li, /sup 7/Li, /sup 10/B, and /sup 11/B ions. The reactions rates are calculated by use of the evaluated data of the LLL Evaluated Nuclear Data Library (ENDL). 5 figures, 5 tables.

Published Hugoniot data for UO/sub 2/ is in error, because the measuring techniques used did not resolve the strong multiple-wave shock-structures present. Hence calculations related to liquid metal, fast-breeder-reactor, excursion analyses based on extrapolations of that data are in serious error. The inclined prism, flash gap, and two-stage gas-gun techniques are used to determine shock-compression parameters for UO/sub 2/ to 300 GPa. The Hugoniot elastic limit for UO/sub 2/ was found to be 5.7 GPa. At higher pressure, a plot of shock vs particle velocity displays a discontinuity between 1.0 < U/sub p/ < 1.8 km/s, which appears to be a manifestation of a solid-solid phase transition. For 1.8 < U/sub p/ < 4.0 km/s, the plot is given by U/sub s/ = 5.8 + 1.28 (U/sub p/ - 1.8).

A series of shipping containment system preliminary concepts for Type B quantities of transuranic waste have been formulated. The concepts were based on hypothetical accident protection requirements, potential waste forms, and selected hardware design/considerations. The concepts consist of suggested waste system containment configurations and construction material suggestions. Analysis of the concepts, based on such features as fabrication ease and cost, utility, and payload efficiency, revealed that concepts utilizing processed waste forms and/or disposable waste packages to provide a major portion of the required accident protection are most favorable.

The following topics are covered: thermodynamic instability of brine, injectivity loss during regular production and injection operations, injectivity loss caused by measures other than regular operations, heat mining and associated reservoir problems in reinjection, pressure maintenance through imported make-up water, suggested solutions to injection problems, and suggested solutions to injection problems: remedial and stimulation measures. (MHR)

Work on the design of an on-site fuel cell total energy system for an apartment building is described. A mass and energy balance was completed for one operating point of a selected power generation sub-system with a power output of 119 kW. Potentially, 87 percent of the LHV of the input fuel is available as bus bar electricity or useful heat. A 2 kW stack of conventional design and a 0.5 kW DIGAS cooled stack have been constructed and are on test at ERC. Renovation of a space for the Westinghouse stack test facility is underway and procurement of equipment has been initiated. The coupled cell temperature - current density analysis has been modified to include the effects of turbulent coolant flow and extended to permit analysis of up to 10 process plates between cooling plates. The REFORM computer program was verified by comparison with data received from the government project manager. A method for predicting carbon deposition was developed and compared with data from the literature.

The transient flow of an isothermal ideal gas from the cavity formed by an underground nuclear explosion is investigated. A two-dimensional finite element method is used in analyzing the gas flow. Numerical results of the pressure distribution are obtained for both the stemming column and the surrounding porous media.

In this third quarterly report of 1979, the University of Tennessee Space Institute (UTSI) reports on significant activity, project and task status, planned research, testing, and development, and conclusions with respect to the Magnetohydrodynamics (MHD) Coal-Fired Flow Facility (CFFF) and the Research and Development Laboratory. This quarter, work on the CFFF progressed with only minor problems. The weather was generally favorable to most outside work. The extent toward completion for all work presently scheduled is now about 93%. In the chemistry laboratory, experiments with pulverized coal and potassium carbonate (K/sub 2/CO/sub 3/) continued. Data indicated that the pulverizing operation unit could be improved by operating at a slightly higher temperature. Doing this, however, should not be a problem. Continued testing of platinum and iridium cladding on anode caps has shown that these materials seem to perform well. The degradation experienced is acceptable and should not pose any problem. This information will be used in developing more oxidant resistant electrodes. Despite initial promise, the Direct Reduction Seed Regeneration process does not seem to be a viable means of seed regeneration. Detailed evaluation of the Tomlinson-Tampella and Formate processes will begin next quarter.

The minimum warm ion density necessary to effectively stablize the DCLC instability in MFTF represents a significant planning requirement. Thus a review of the theoretical predictions for MFTF stabilization is presented here including the recently revised (a/sub i//r/sub p/) scaling determined from tests with 2XIIB. For the assumptions given the total streaming current requirements range from 1500 to 2800 A, for T/sub e/ predicted from .66 to 1 keV and E/sub i/ approx. 50 keV.

Dynamic calibration is a measurement control technique designed to facilitate the use of nondestructive assay for the control and accounting of special nuclear material. The implementation of dynamic calibration requires selection of an appropriate control measurement and sampling plan to provide traceability for the measurement system. A general sampling plan for use when the control measurement is an independent assay is presented with examples.

The purpose of this report is to summarize Phase I efforts for marketing by-products from the Industrial Fuel Gas Demonstration Plant (IFGDP). The scope of inquiry over the last year was not intended to be intensive, but rather to conduct a thorough preliminary investigation to define the marketing parameters and potential revenue available from the sale of plant by-products. The first section discusses the impact of by-product revenue on plant economics and potential for local area development. Succeeding sections discuss particular by-products, the intended market, and economic calculations for potential yearly revenue. Three generic by-products have been identified: recovered liquid sulfur, ash agglomerates, and industrial gases (nitrogen, argon, and carbon dioxide). The sale of IFGDP by-products has the potential for significant impact in several ways. First, the revenue generated can lower operating costs significantly and thereby reduce IFG gas cost. Second, by-products can stimulate the local economy by increasing the availability of certain raw materials and offering a lower than existing market price for these materials and, third, availability of certain by-products in large volumes may induce new business to locate in the Memphis/Mid-South area. The results of this survey show that by-product volumes will be significantly greater than the …

Since ammonium nitrate manufacture is dependent on natural gas, a shortage in natural gas could lead to a critical shortage in coal by limiting the availability of ammonium nitrate for blasting. The purpose of this study was to assess the future availability of ammonium nitrate and to evaluate the potential of alternative oxidizers not dependent upon natural gas for use in blasting agents. Increased storage capacities and rapidly increasing levels of relativey cheap imported ammonia appear to ensure the availability of adequate levels of ammonium nitrate in the near future. In the longer time frame, rising energy costs have increased the potential for basing ammonia production on alternative sources of hydrogen as well as obtaining natural gas from relatively unlimited unconventional sources. While still somewhat uncertain, such unconventional sources appear to have sufficient potential to ensure the availability of ammonium nitrate even long term. However, there are several oxidizers that could be considered as possible replacements for ammonium nitrate if needed. After a critical evaluation two possible alternatives are recommended for further study: the use of sodium nitrate as a partial replacement and the development of a new type of blasting agent based upon water as the main oxidizer.