This study was designed to observe the feasibility of the use by NRC licensees of the tissue equivalent proportional counter (TEPC) system as a neutron monitoring instrument. Laboratory tissue equivalent proportional counters were irradiated using /sup 252/Cf sources at NBS and PNL and were irradiated inside containment of four operating nuclear power plants (two boiling water reactors and two pressurized water reactors). On the average, neutron dose-equivalent rates determined using the TEPC were 1.05 times the calculated dose-equivalent rates for the bare and moderated /sup 252/Cf sources and 0.86 times the dose-equivalent rates determined using the multispheres inside containment of nuclear power plants. Further, neutron dose equivalent rates determined using portable remmeters were an average of 1.71 times the dose equivalent determined using the multispheres inside the containment of nuclear power plants. It was observed that while electronic noise from temperature and vibrational effects inside containment prohibited an adequate measure of absorbed dose from gammas, the measurement of neutron absorbed dose was unaffected by these environmental parameters. It is recommended that for use inside containment at nuclear power plants: (1) the laboratory scale TEPC is the superior technique for accurate determination of neutron dose equivalent, (2) for remmeters similar to …

Construction of the experiment cavern on the 27th level of the SOUDAN iron mine in northern Minnesota began early this year and will be complete early in 1985. The first 1200 tons of the detector itself is also under construction in the US and UK; installation will begin in mid 1985. Physics exploitation will begin early in 1986 and the first 1200 ton module will be complete early in 1987. The detector may be expanded to between 3 and 5 such modules in the cavern. The detector is an iron tracking calorimeter (rho = 2) consisting of stacks of corrugated steel sheets each 1.2 mm thick. The corrugations form hexagonal channels 1 m long and 16 mm in diameter. A uniform electric field along these channels is provided by the voltage grading arising from the constant standing current in the Hytrel tubes (rho = 2 x 10/sup 12/ ..cap omega.. cm) that line each channel. The tubes are insulated from the steel by sheets of mylar. Ionization in the gas in the tubes drifts in the uniform field to the end of the tube where it is amplified linearly and detected by a matrix of anode wires and cathode strips. …

The purpose of this Public Participation Plan is to describe the Department of Energy's plan for involving the public in the decision-making process required by the National Environmental Policy Act (NEPA) of 1969 as related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by congress in the Uranium Mill Tailings Radiation Control Act of 1978, PL95-604. The Act provides for a cooperative effort with affected states and Indian tribes for the cleanup of designated inactive uranium mill tailings sites and associated vicinity properties, which are located in ten western states and in Pennsylvania. The Act was amended in 1982 to also include vicinity properties contaminated with residual radioactive material in Edgemont, South Dakota.

The Public Information Plan is intended to be used in conjunction with the DOE-UMTRA Project Public Participation Plan'' to describe the Department of Energy's plan for involving the public in the decision-making process related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by Congress in the Uranium Mill Tailings Radiation Control of Act of 1978, PL95-604. The Act provides for a cooperative effort with affected states and Indian tribes for the cleanup of designated abandoned or inactive uranium mill tailings sites. The objective of the Public Information Plan of the UMTRA Project is timely and sufficient dissemination of factual information to promote understanding of the project by federal, state, and local officials, the media, special interest groups, and the general public; and thereby to encourage informed participation in the project by the public and government officials. The Uranium Mill Tailings Radiation Control Act provides for public involvement in remedial action planning, with special consideration given to landowners, Indian tribes, and the states. According to the Act, the Secretary of Energy shall hold public hearings in the states where processing sites, vicinity properties, and disposal sites are located. Public participation in the UMTRA Project will not, …

A workshop was conducted to discuss problem areas associated with developing carcinogen guidelines. Session topics included (1) definition of a carcinogen for regulatory purposes; (2) potency; (3) risk assessment; (4) uncertainties; (5) de minimis quantity; and (6) legal and regulatory issues. Separate abstracts have been prepared for individual papers. (ACR)

The objective of these studies is to evaluate the technical and economic feasibility of producing specific gas products by catalytic gasification of biomass. Catalyst performance is a key factor in the feasibility of catalytic gasification processes. The results of studies designed to gain a fundamental understanding of catalytic mechanisms and causes of deactivation, and discussion of the state-of-the-art of related catalytic processes are presented. Experiments with primary and secondary catalysts were conducted in a 5-cm-diameter, continuous-wood-feed, fixed-catalyst-bed reactor. The primary catalysts used in the experiments were alkali carbonates mixed with the biomass feed; the secondary catalysts included nickel or other transition metals on supports such as alumina, silica, or silica-alumina. The primary catalysts were found to influence wood pyrolysis as well as the char/steam reaction. Secondary catalysts were used in a fixed-bed configuration to direct gas phase reactions. Results of the performance of these catalysts are presented. Secondary catalysts were found to be highly effective for conversion of biomass to specific gas products: synthesis gases and methane-rich gas. With an active catalyst, equilibrium gas composition are obtained, and all liquid pyrolysis products are converted to gases. The major cause of catalyst deactivation was carbon deposition, or coking. Loss of surface …

The rationale for recycling SRC in the SRC-I Demonstration Plant focuses on the need for maintaining process solvent yield and quality. As noted in previous reports, the flow through the scaled-up reactor of the Demonstration Plant will be approximately 10 times faster than that in the Wilsonville Pilot Plant reactor - and a computer study (a sequential kinetic model devised by Air Products) has indicated that the faster rate, in reducing the severity of the reaction, will thereby reduce solvent yield and quality. But the same computer study has also predicted that recycling SRC will generate additional solvent of adequate quality. SRC comes in several different compositions. Typically, in the Phase 0 filtration case, SRC is a mixture of approximately 5% oils, 55% asphaltenes, and 40% preasphaltenes. In the Kerr-McGee case for the Demonstration Plant, a light SRC (LSRC) is generated from the Third Stage Settler and a heavy SRC (HSRC) from the Second Stage Settler. The effects of recycling these fractions, mixtures of LSRC, coal and solvent were run through the Air Products Coal Process Development Unit (CPDU) under conditions simulating those of the Demonstration Plant. The results were: Oil formation increased; the hydrogen content of the oil and …

The radiation-measurement team of the Weapons Engineering Division at Lawrence Livermore National Laboratory (LLNL) measured neutron and gamma dose and spectra on the Little Boy replica at Los Alamos National Laboratory (LANL) in April 1983. This assembly is a replica of the gun-type atomic bomb exploded over Hiroshima in 1945. These measurements support the National Academy of Sciences Program to reassess the radiation doses due to atomic bomb explosions in Japan. Specifically, the following types of information were important: neutron spectra as a function of geometry, gamma to neutron dose ratios out to 1.5 km, and neutron attenuation in the atmosphere. We measured neutron and gamma dose/fission from close-in to a kilometer out, and neutron and gamma spectra at 90 and 30/sup 0/ close-in. This paper describes these measurements and the results. 12 references, 13 figures, 5 tables.

Harmonic generation and parametric decay are examined in a toroidal ACT-I plasma using electrostatic plate antennas. The harmonic generation, which is consistent with sheath rectification, is sufficiently strong that the nonlinearly generated harmonic modes themselves decay parametrically. Resonant and nonresonant parametric decay of the second harmonic are observed and compared with uniform pump theory. Resonant decay of lower hybrid waves into lower hybrid waves and slow ion cyclotron waves is seen for the first time. Surprisingly, the decay processes are nonlinearly saturated, indicating absolute instability.

Chemical data for two sediment cores from the East Waterway of Everett, Washington, indicate that 20 to 30 cm of contaminated sediments are accumulating per year. The concentrations of several heavy metals (Pb, Hg and Cu), polychlorinated biphenyls (PCBs) and petroleum hydrocarbons increase with depth in the sediments suggesting contamination of this waterway has varied by as much as a factor of 10 during the last 5 years. 7 references, 9 figures, 12 tables.

The objective of this program is to examine slags formed as a result of firing coals with varying concentration levels, size distribution, and orientation of pyrite with regard to mineral matter in the coal in a laboratory furnace. The program tasks are: (1) selection of eight candidate coals; (2) chemical characterization of the coal samples and identification of the pyrite size, distribution, and orientation with respect to other mineral matter and concentration levels; (3) testing of the candidate coals in a laboratory furnace; (4) chemical and physical characterization of the slag and fly ash samples created by the impurities in the coal sample; (5) influence of coal beneficiation on furnace slagging; and (6) analysis of data and identification of parameters influencing the contribution of pyrite to slagging problems. Results of analysis of two coals, Illinois No. 5 Gallatin County, Illinois and Lower Kittaning Clarion County, Pennsylvania, are presented. Examination of the morphology of furnace slag deposited in the 100 lb/hr combustor, as well as industrial furnace, revealed reocurring crystals of iron of pyrite origin on the surface of the deposit. The cubic, octahedron and cubic/octahedron crystals are similar in size and structure to pyrite crystals occasionally found in coal. To …

The present backlog of irradiated reactor fuel leads to projections that no fuel out of the reactor less than 10 years need be reprocessed prior to the year 2000. The only radioiodine present in such aged fuel is /sup 129/I (half-life 1.6 x 10/sup 7/ y). The /sup 131/I initially present in the fuel decays to insignificance in the first few hundred days post-reactor. The /sup 129/I content of irradiated fuel is about 1 Ci per gigawatt-year of electricity generated (Ci/GW(e)-y). The US EPA has specified, in 40 CFR 190, a release limit for /sup 129/I of 5 mCi/GW(e)-y. Thus a retention factor (RF) of 200 for /sup 129/I at the fuel reprocessing plant (FRP) is required. Experience indicates that RF values obtained under actual FRP operating conditions can average as little as 10% of experimentally determined RF values. Therefore processes theoretically capable of achieving RF values of up to 10/sup 4/ have been investigated. The US EPA has also specified in 40 CFR 90 a thyroid dose limit of 75 mrem/y for a member of the general public. This dose limit could be readily met at a typical FRP site with an RF value of about 10 or less. …

The dissolution of plutonium dioxide in nitirc acid (HNO/sub 3/) at high hydrofluoric acid (HF) concentrations has been investigated. Dissolution rate curves were obtained using 12M HNO/sub 3/ and HF at concentrations varying from 0.05 to 1.0 molar. The dissolution rate increased with HF concentration up to 0.2M and then decreased at higher concentrations. There was very little plutonium dissolved at 0.7 and 1.0M HF because of the formation of insoluble PuF/sub 4/. Various oxidizing agents were added to 12M HNO/sub 3/-1M HF dissolvent to oxidize Pu(IV) to Pu(VI) and prevent the formation of PuF/sub 4/. Ceric (Ce(IV)) and silver (Ag(II)) ions were the most effective in dissolving PuO/sub 2/. Although these two oxidants greatly increased the dissolution rate, the rates were not as rapid as those obtained with 12M HNO/sub 3/-0.2M HF.

Experiments were performed on the PDX tokamak to study plasma heating and ..beta.. scaling with higher power, near-perpendicular neutral beam injection. The data taken during these experiments were analyzed using a time-dependent data interpretation code (TRANSP) to study the transport and thermal confinement scaling over a wide range of plasma parameters. This study focuses on results from experiments with D/sup 0/ injection into H/sup +/ plasmas using graphite rail limiters, a = 40 to 44 cm, R = 143 cm, I/sub p/ = 200 to 480 kA, B/sub T/ = 0.7 to 2.2 T, and typically anti n/sub e/ = 2.5 to 4.2 x 10/sup 13/ cm/sup -3/. The results of this study indicate that for both ohmic and neutral beam heated discharges the energy flow out of the plasma is dominated by anomalous electron losses, attributed to electron thermal conduction. The ion conduction losses are well described to electron thermal conduction. The ion conduction losses are well described by neoclassical theory; however, the total ion loss influences the power balance significantly only at high toroidal fields and high plasma currents.

Mathematical models and numerical methods for a two-dimensional porous body simulation of steady state and transient thermal-hydraulics conditions in LMFBR subassemblies resulting in the TWIST computer code are presented. Comparison of calculated results to steady state and transient out-of-pile sodium experiments show good agreement for cross-assembly temperature distributions for a wide range of heat transfer and flow conditions.

For a synchrotron radiation facility to get high spectral brilliance it is desirable to have small emittance of the electron beam in the storage ring. Ways of improving beam emittance by optimizing the lattice are discussed.

A simple method for the investigation of thermodynamic (substance) similarity in the two-phase domain is introduced based on the assumptions of a simplified model fluid. According to this method, the investigation of the conditions for thermodynamic similarity between substances in the two-phase region reveals the important role the latent heat of evaporation (h/sub fg/) plays in the definition of the property scales. These greatly influence the dynamic and geometric similarity of the process under investigation. The introduction of the thermodynamic similarity property scales into the energy conservation equations for a certain process (e.g., flow up a geothermal well) brings forth a thermodynamic length scale and kinetic energy scale. Refrigerant 114 has been examined for similarity with water substance according to this method and found to be adequate for geothermal well simulation in the laboratory. Low pressures and temperatures and a substantial reduction of mass flow rates and geometric scales are a few of the advantages of using R114 for such experiments.

This report covers work done during FY 1983 by the staff of the Energy Division and its subcontractors and by colleagues in other Oak Ridge National Laboratory divisions working on Energy Division projects. The work can be divided into four areas: (1) analysis and assessment, (2) models and data systems, (3) research to improve the efficiency of energy use and to improve electric power transmission and distribution, and (4) research utilization. Support came principally from the US Department of Energy (DOE), the US Nuclear Regulatory Commission, and the US Department of Defense, but also from a number of other agencies and organizations. Analysis and assessment included work on (a) environmental issues, including those deriving from the preparation of environmental impact statements; (b) energy and resource analysis; and (c) emergency preparedness. The models and data systems area involved research on evaluating and developing energy, environment, and engineering simulation models and on devising large data management systems, evaluating user data requirements, and compiling data bases. Research on improving the efficiency of energy use was focused primarily on the buildings and electricity sectors. A major effort on heat pump technology, which includes both heat-activated and electrically driven systems, continues. An important aspect of …

Recent theories and experiments challenge the applicability of linear stability theory near the onset of buoyancy-driven (Rayleigh-Benard) convection. This stability theory, based on small perturbations of infinite parallel rolls, is found to miss several important features of the convective flow. The reason is that the lateral boundaries have a profound influence on the possible wave numbers and flow patterns even for the largest cells studied. Also, the nonlinear growth of incoherent unstable modes distorts the rolls, leading to a spatially disordered and sometimes temporally nonperiodic flow. Finally, the relation of the skewed varicose instability to the onset of turbulence (nonperiodic time dependence) is examined. Linear stability theory may not suffice to predict the onset of time dependence in large cells close to threshold.

This is Volume II of Photovoltaic Module Encapsulation Design and Materials Selection: a periodically updated handbook of encapsulation technology, developed with the support of the Flat-Plate Solar Array Project (FSA), managed for the Department of Energy (DOE) by the Jet Propulsion Laboratory. Volume II describes FSA encapsulation technology developed between June 1, 1982, and January 1, 1984. Emphasis during this period shifted from materials development to demonstration of reliability and durability in an outdoor environment; the updated information in this volume reflects the developing technology base related to both reliability and encapsulation process improvements.

Data on residential loads has been collected from four residences in real time. The data, measured at 5-second intervals for 53 days of continuous operation, were statistically characterized. An algorithm was developed and incorporated into the modeling code SOLCEL. Performance simulations with SOLCEL using these data as well as previous data collected over longer time intervals indicate that no significant errors in system value are introduced through the use of long-term average data.

Both articles in this report have been entered individually into EDB and ERA. (LTN)

This report documents a review, performed by the Pacific Northwest Laboratory (PNL), of the Transamerica Delaval, Inc. (TDI) Diesel Generator Owner's Group Program Plan. This report was prepared as part of the technical support PNL is providing to the US Nuclear Regulatory Commission (NRC), Division of Licensing, on matters pertaining to the reliability of TDI diesel generators as emergency power sources for safety-related nuclear systems. The report presents the comments and conclusions reached by PNL, with the advice and counsel of five diesel engine consultants, on the principal elements of the Owners' Group Plan: Generic Problem Resolution, Design Review/Quality Revalidation, and Engine Testing and Inspection. Also included are PNL's comments on the related issues of Surveillance and Maintenance, and Administrative Controls. The conclusions drawn from PNL's evaluation of these issues form the basis for two additional topics addressed in the report: Critical Elements Required to Establish Diesel Engine Operability and Reliability, and Considerations for Interim Licensing.

A thermally stratified flow produced by a thermal transient passing through a horizontal elbow gives rise to large thermal fluctuations on the inner curvature wall of the downstream piping. These fluctuations were measured in a specially instrumented horizontal pipe and elbow system on a test set-up using water in the Mixing Components Technology Facility. This study is part of a larger program which is studying the influence of thermal buoyancy on general reactor component performance. This paper discusses the influence of pipe flow generated thermal oscillations on the structured thermal stresses induced in the pipe walls.