This report presents the results of work performed from October 1, 1980 through December 31, 1980 on the Advanced Gas- Cooled Nuclear Reactor Materials Evaluation and Development Program.

The South Coast Technology Volkswagen Rabbit, an electric vehicle manufactured by South Coast Technology of Santa Barbara, California was tested at the Jet Propulsion Laboratory's (JPL) dynamometer facility in Pasadena and at JPL's Edwards Test Station (ETS) located near Lancaster, California. The tests were conducted between April and July, 1979. These tests were performed to characterize certain parameters of the South Coast Rabbit and to provide baseline data that will be used for the comparison of near-term batteries that are to be incorporated into the vehicle. The vehicle tests were concentrated on the electrical drive system; i.e., the batteries, controller, and motor. The tests included coastdowns to characterize the road load, maximum effort acceleration, and range evaluation for both cyclic constant speed conditions. A qualitative evaluation of the vehicle was made by comparing its constant speed range performance with those vehicles described in the document State of the Art assessment of Electric and Hybrid Vehicles. The Rabbit performance was near to the best of the 1977 vehicles.

The objective of the BNL Neutral Beam Program is to develop a 250 keV neutral beam system suitable for heating and other experiments in toroidal or mirror plasma devices. The system is based on acceleration and neutralization of negative hydrogen ions produced in and directly extracted from a source. The objective of source studies is to develop a module delivering 10 A of negative ion currents, with pulse lengths ranging from several seconds duration up to a steady-state operation. The extracted current density should be several hundred mA/cm/sup 2/, and the source should operate with power and gas efficiencies acceptable from the beam line point of view. The objective of beam extraction and transport studies is to design a system matching the 10 A source module to the acceleration stage. The 250 keV acceleration studies cover several options, including a d.c. close-coupled system, a large aperture d.c. system matched to the source by a bending magnet, a multiaperture d.c. system following a multiaperture strong focusing transport line, and a MEQALAC structure.

In response to Task A.63 of the International Safeguards Project Office (ISPO), to upgrade measurement technology used by the International Atomic Energy Agency (IAEA), a portable data-reduction microprocessor was designed and programmed which allows in-field reduction of gamma-ray spectra and interfaces with the IAEA's multichannel analyzers - the 1000 or 2000-channel memory Silena BS27/N. This report describes the components used in assembling the microprocessor unit: hardware, software used to control the unit, and the mathematical formulation used to obtain isotopic ratios from the gamma-ray data. A simple overview is presented of the unit's operation and the results of tests on gamma-ray spectra that sought to verify the unit's operating characteristics and to determine the precision and effectiveness of the software developed for data reduction.

Systems that reduce energy usage and are economically viable in the citrus fruit processing industry are identified. The preliminary results of Phase I are presented. Alternative systems to be considered are classified and denoted as central, modular, integrated, and combined. Progress is reported on the central and modular systems. (MCW)

A new electric gun system was constructed for use in high-pressure EOS studies. The system is powered by a 100 kV, 15.6 ..mu..F capacitor bank. At 100 kV charging voltage the system inductance is 23 nH. This system has driven 0.3 mm-thick Kapton projectiles to > 20 km/s and 0.3 mm Kapton/30 ..mu..m Ta projectiles to approx. 10 km/s. Projectile velocity is modeled phenomenlogically by an electrical Gurney model.

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

The rates for a number of reactions producing certain stable nuclides, such as /sup 3/He and /sup 4/He, and fission in the moon are calculated for galactic-cosmic-ray particles and for solar protons. Solar-proton-induced reactions with bromine usually are not an important source of cosmogenic Kr isotopes. The /sup 130/Ba(n,p) reaction cannot account for the undercalculation of /sup 130/Xe production rates. Calculated production rates of /sup 15/N, /sup 13/C, and /sup 2/H agree fairly well with rates inferred from measured excesses of these isotopes in samples with long exposure ages. Cosmic-ray-induced fission of U and Th can produce significant amounts of fission tracks and of /sup 86/Kr, /sup 134/Xe, and /sup 136/Xe, especially in samples with long exposures to cosmic-ray particles.

A two-year research and development program was initiated in April of 1979 to study the hydrochlorination of silicon tetrachloride and metallurgical grade (m.g.) silicon metal to trichlorosilane, 3 SiCl/sub 4/ + 2H/sub 2/ + Si in equilibrium 4 SiHCl/sub 3/. A laboratory scale pressure reactor was constructed to study this reaction at pressures up to 500 psig. Reaction kinetic measurements were carried out as a function of reactor pressure, reaction temperature and H/sub 2//SiCl/sub 4/ feed ratio. Based on the reaction kinetic data, the hydrochlorination of SiCl/sub 4/ and m.g. silicon metal is found to be an efficient process to produce SiHCl/sub 3/ in good conversions and in high yields. Copper is an effective catalyst. Results of a corrosion study show that conventional nickel-chromium alloys are suitable material of construction for the hydrochlorination reactor. The hydrochlorination reaction is relatively insensitive to external process parameters such as silicon particle size distribution and the impurities in the m.g. silicon metal.

This report covers the work carried out during the January-March 1981 quarter of the program. Preparations are being made to ready the equipment for the moisture tolerance test program. The main effort described pertains to the redesign and procurement of the main shaft bearing and seal system. To enhance the chances of achieving the program objectives, the recommendation was made by Lockheed to use a conventional roller bearing for the present program instead of the advanced water-lubricated bearing. Nevertheless, the need exists for better long-term solutions to the bearing and seal problem, especially in view of the eventual requirement to scale the equipment to larger sizes. It is recommended that the program proceed as planned.

The method is based on counting the 186-keV gamma rays emitted by /sup 235/U using a Pb-collimated Ge(Li) detector. Measurements of fifty UF/sub 6/ product and feed cylinders reveal the following precisions and counting times: Product - 2S, 0.98% (600 s); Feed - 2S, 0.48% (2500 s); Product - 1S, 0.62% (1000 s); Feed - 1S, 0.73% (3000 s). A 1% precision is desired for variables - attributes verification measurements of /sup 235/U assay in UF/sub 6/ sample cylinders for safeguards inspections by the International Atomic Energy Agency (IAEA). Statistically, these measurements stand between fine, high-precision (or variables) measurements and gross, low-precision (or attributes) ones. Because of their intermediate precisions, the variables-attributes measurements may not require analysis of all samples, and this could result in significant savings of IAEA inspector time. Although the precision of the above results is satisfactory, the average relative differences between gamma-ray and mass-spectrometric determinations for the last two sets of measurements (1S cylinders) have positive biases.

The Automated Lamination Station is mechanically complete and is currently undergoing final wiring. The high current driver and isolator boards have been completed and installed, and the main interface board is under construction. The automated vacuum chamber has had a minor redesign to increase stiffness and improve the cover open/close mechanism. Design of the Final Assembly Station has been completed and construction is underway.

The objective of the Spent Fuel Stabilizer Materials Program is to identify, test, select, and qualify stabilizer materials for use in the design of spent fuel waste packages. Emphasis is placed on the selection of stabilizer materials that exhibit minimal interaction with the other waste package components. The spent fuel stabilizer fill process screening test was completed. This test measured the interaction of candidate metal stabilizers with LWR fuel cladding during stabilizer emplacement at elevated temperatures. While the test focused on screening of stabilizer materials, interaction information with a candidate canister material (1018 carbon steel) was also generated and will be useful in future considerations.

The objective of the Spent Fuel Stabilizer Materials Program is to identify, test, select, and qualify stabilizer materials for use in the design of spent fuel waste packages. Emphasis is placed on the selection of stabilizer materials with minimal interactions. The preliminary screening of candidate spent fuel stabilizer materials was completed and reported to the Office of Nuclear Waste Isolation in November 1980. Based on criteria set for thermally induced stresses, material cost, and material availability, an initial list of potential stabilizers was reduced to 34 that are recommended for additional screening tests. The spent fuel stabilizer temperature limit test was completed during this report period. Tests were conducted to establish a conservative temperature limit for spent light water reactor (LWR) fuel during the stabilizer emplacement process. Melting of metals and metal alloys, fusing of glass stabilizers,or other possible emplacement processes may require elevation of the spent fuel temperature above levels desirable for maintaining fuel rod integrity (intact cladding) or reasonable inter-rod spacing for stabilizer flow. This test was conducted to establish the temperature below which these concerns would not exist. Stabilizers that require emplacement process temperatures above the limit will be eliminated from the screening program.

The focus is on electric power production using geothermal resources greater than 150/sup 0/C because this form of geothermal energy utilization has the most serious health-related consequences. Based on measurements and experience at existing geothermal power plants, atmospheric emissions of noncondensing gases such as hydrogen sulfide and benzene pose the greatest hazards to public health. Surface and ground waters contaminated by discharges of spent geothermal fluids constitute another health hazard. It is shown that hydrogen sulfide emissions from most geothermal power plants are apt to cause odor annoyances among members of the exposed public - some of whom can detect this gas at concentrations as low as 0.002 parts per million by volume. A risk assessment model is used to estimate the lifetime risk of incurring leukemia from atmospheric benzene caused by 2000 MW(e) of geothermal development in California's Imperial Valley. The risk of skin cancer due to the ingestion of river water in New Zealand that is contaminated by waste geothermal fluids containing arsenic is also assessed. Finally, data on the occurrence of occupational disease in the geothermal industry are summarized briefly.

The edge-defined film-fed growth (EFG) process is a silicon-sheet technology option that is being developed for the Low-Cost Solar Array (LSA) Project. A sensitivity analysis is presented of the process add-on price in terms of cost parameters such as equipment, space, direct labor, materials and utilities, and the production parameters such as growth rate, process yield and duty cycle, using a computer program developed specifically to do the sensitivity analysis with IPEG.

Run ZBF was conducted to determine the amount of sulfur and nitrogen removal from SRC-I/process solvent mixture in the absence of a hydrotreating catalyst. Negligible nitrogen and sulfur removal resulted from this experiment. The hydrogen content of the coal liquid increased slightly over that of the feedstock. In similar studies using other coal liquids some sulfur removal (10 to 40%) was noted under non-catalyzed conditions. Several commercial NiMo supported catalysts were analyzed for silica contents using atomic absorption. These results revealed that catalysts with large micropore size structures also contain high silica content (up to 22.5 weight percent). Several short duration runs (12 to 110 hours) were conducted in the CLTU to gather data on catalyst coking mechanisms. Using the SRC material mixed with a process solvent or creosote oil (30 weight percent SRC), solid materials were observed to form and precipitate in the latter portions of the reactor bed. The reactor system was modified to prevent the accumulation of these incompatible solids which would result in premature termination of the experimental runs. In the catalyst regeneration study (HDN-30, NiMo), a spent catalyst was regenerated and then used to hydrotreat a coal liquid consisting of 10% Synthoil II liquid mixed …

Absorption spectra obtained from SmBr/sub 3/, SmBr/sub 2/, and Sm0Br were used in identifying the samarium species in several mixed-valence Sm(II/III) compounds produced by H/sub 2/ reduction of SmBr/sub 3/. The nature of the absorption of Sm0Br made it possible to detect even traces of Sm0Br in the Sm bromides.

Major accomplishments are listed: 1. It was found that molten sodium hydroxide (in place of mixed sodium and potassium hydroxides) followed by dilute sulfuric acid wash gave Gravimelt coal with the usual amount of sulfur and mineral matter removal but there was no MAF heat content loss over the small amount required for replacement of sulfur atoms by oxygen atoms in the coal structure - e.g., these samples had both measured heat content and MAF heat content in excess of 1400 Btu/lb. Therefore, the selectivity of the Gravimelt Process appears to be very high. 2. It was found that demineralized and desulfurizd Gravimelt coal has significantly less alkali metals content than the input coal. 3. Kentucky No. 11 coal was reduced in sulfur content to a level of 0.10 lbs of sulfur (0.20 lbs of sulfur dioxide)/10/sup 6/ Btu with an ash content of 0.21% in a cumulative reaction time of 60 minutes. This represents a 96% reduction in sulfur and a 97% reduction in ash. This product is significantly lower in sulfur content and ash than are typical synthetic or conventional liquid boiler fuels. 4. The Gravimelt Process was tested on Illinois No. 6 coal giving essentially identical results …

A general expression has been derived to enable calculation of the calibration error resulting from simulator-solar AMX spectral mismatch and from reference cell-test cell spectral mismatch. The information required includes the relative spectral response of the reference cell, the relative spectral response of the cell under test, and the relative spectral irradiance of the simulator (over the spectral range defined by cell response). The spectral irradiance of the solar AMX is assumed to be known.

This report describes the basic parameters which directly influence the behavior of a coal slurry pipeline transportation system and determine the limitations of the system performance. The purpose of this technology assessment is to provide an identification and understanding of the critical factors which must be given consideration in the design and evaluation of such a slurry haulage system intended for use in an underground coal mine. The slurry haulage system will be utilized to satisfy the transportation requirements of conveying, in a pipeline, the coal mined by a continuous mining machine to a storage location near the mine entrance or to a coal preparation plant located on the surface. Coal-water slurries, particularly those consisting of homogeneous suspensions of small particles, frequently behave as non-Newtonian, Bingham-plastic fluids. For successful operation, slurry transport systems should be designed to operate in the turbulent flow regime and at a flow rate at least 30% greater than the deposition velocity. The deposition velocity is defined as the slurry flow rate at which the solid particles tend to settle in the pipe. Due to the importance of accurately determining the deposition velocity and the uncertainties of current methods for predicting the deposition velocity of coarse …

Steady-state phase relations in the system UO/sub 2 + x/-CeO/sub 2/-ZrO/sub 2/-ThO/sub 2/ were determined for application to phase relations in the high-level crystalline ceramic nuclear waste form Supercalcine-Ceramics. Samples were treated at 1200/sup 0/C at an oxygen partial pressure of 0.21 atm and a total pressure of 1 atm. Phase assemblages were found to be composed of cubic solid solutions of the flourite structure type, solid solutions based on ZrO/sub 2/, and orthorhombic solid solutions based on U/sub 3/O/sub 8/.

A study of basic combustion and pollutant formation processes for pulverized solid fossil fuels has been initiated. The solid fossil fuels under consideration for this research include such solid fuels as non-bituminous coal types, solvent refined coal, combustion char, petroleum coke, oil shale and tar sand. The potential industrial application of pulverized fuels other than coal provides some promise for relief from present and future conventional fuel shortages. Utilization problems with these fuels such as flame stability, fuel handling, pollutant emission and ash and slag formation in large-scale furnaces may be fundamentally addressed in laboratory reactors using properly scaled operating variables. An extensive literature search was begun to assess current knowledge relative to utilization of these fuels. This review will provide a basis for selection of three solid fuels for testing. Pertinent information from industrial contacts will also be used in the fuel selection. The criteria to be used in the selection of these fuels include availability for economic industrial use, adaptability, grindability, flame stability, entrainability, uniformity, applicability to direct firing with air, solidity with heating, availability to the BYU Combustion Laboratory, cost, other physical characteristics affecting their use, industrial input and recommendations, and DOE approval. The existing laboratory coal …

Radiation effects in insulating solids are discussed in a general way as an introduction to the quite sparse published work on radiation effects in candidate nuclear waste forms other than glasses. Likely effects of transmutation in crystals and the chemical mitigation strategy are discussed. It seems probable that radiation effects in solidified HLW will not be serious if the actinides can be wholly incorporated in such radiation-resistant phases as monazite or uraninite.