The three-dimensional eddy current transient field problem is formulated first using the U-V method. This method breaks the vector Helmholtz equation into two scalar Helmholtz equations. Null field integral equations and the appropriate boundary conditions are used to set up an identification matrix which is independent of null field point locations. Embedded in the identification matrix are the unknown eigenvalues of the problem representing its impulse response in time. These eigenvalues are found by equating the determinant of the identification matrix to zero. When this initial forcing function is Fourier decomposed into its spatial harmonics, each Fourier component can be associated with a unique eigenvalue by this technique. The true transient solution comes through a convolution of the impulse response so obtained with the particular external field decay governing the problem at hand. The technique is applied to the FELIX cylinder experiments; computed results are compared to data. A pseudoanalytic confirmation of the eigenvalues so obtained is formulated to validate the procedure.

In the annual hydrologic cycle, snowmelt is the most significant event at Imnavait Creek located near Toolik Lake, Alaska. Precipitation that has accumulated for more than 6 months on the surface melts in a relatively short period of 7 to 10 days once sustained melting occurs. During the ablation period, runoff dominates the hydrologic cycle. Some meltwater goes to rewetting the organic soils in the active layer. The remainder is lost primarily because of evaporation, since transpiration is not a very active process at this time. Following the snowmelt period, evapotranspiration becomes the dominate process, with base flow contributing the other watershed losses. It is important to note that the water initally lost by evapotranspiration entered the organic layer during melt. This water from the snowpack ensures that each year the various plant communities will have sufficient water to start a new summer of growth.

This report summarizes the NRC/EPRI coordinated effort to develop design requirements for a standardized advanced light water reactor (ALWR) and the procedures for screening and applying new generic safety issues to this program. The end-product will be an NRC-approved ALWR Requirements Document for use by the nuclear industry in generating designs of LWRs to be constructed for operation in the 1990s and beyond.

Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of potential airborne releases caused by accidents. Aerosols generated by accidents are being investigated by Pacific Northwest Laboratory to develop methods for estimating source terms from these accidents. Experiments were run by spilling viscous solutions and slurries to determine the mass and particle-size distribution of the material made airborne. In all cases, 1 L of solution was spilled from a height of 3 m. Aqueous solutions of sucrose (0 to 56%) gave a range of viscosities from 1.3 to 46 cp. The percent of spill mass made airborne from the spills of these solutions ranged from 0.001 to 0.0001. The mass of particles made airborne decreased as solution viscosity increased. Slurry loading ranged from 25 to 51% total solids. The maximum source airborne (0.0046 wt %) occurred with the slurry that had the lightest loading of soluble solids. The viscosity of the carrying solution also had an impact on the source term from spilling slurries. The effect of surface tension on the source term was examined in two experiments. Surface tension was halved in these spills by adding a surfactant. The maximum weight percent airborne from …

The Deep Salton Sea Scientific Drilling Program (DSSSDP) was conducted in Imperial County of California at the Southeastern edge of the Salton Sea. Emphasis was on the acquisition of scientific data for the evaluation of the geological environment encountered during the drilling of the well. The scientific data acquisition activities consisted of coring, running of numerous downhole logs and tools in support of defining the geologic environment and conducting two full scale flow tests primarily to obtain pristine fluid samples. In addition, drill cuttings, gases and drilling fluid chemistry measurements were obtained from the drilling fluid returns concurrent with drilling and coring operations. The well was drilled to 10,564 feet. This report describes the field portions of the project and presents an analysis of the time spent on the various activities associated with the normal drilling operations, scientific data gathering operations and the three major downhole problem activities - lost circulation, directional control and fishing.

Analysis of 59 time series from ten small magnitude earthquakes recorded in 1981 by portable digital seismic systems at the southern Nevada Test Site (NTS) yielded several significant results. We find that moment magnitude (M/sub L/) (local magnitude determined from seismic moment) correlates closely with coda duration magnitudes M/sub d/ determined by the Southern Great Basin Seismic Network (SGBSN). Further, local magnitude M/sub W A/ computed from displacement seismograms simulating Wood-Anderson response are, on average, 0.38 magnitude units larger than M/sub d/ and 0.44 magnitude units larger than (M/sub L/). Another result is that stress drops for the ten earthquakes are significantly smaller than typical stress drops for earthquakes of similar seismic moment in California. Similarly, determinations of the peak ground motion parameter Rv are up to 10 to 20 times smaller than a previously determined empirical formula relating Rv to seismic moment. We conclude that seismic waves from southern Nevada Test Site earthquakes suffer from significant anelastic attenuation, possibly in the near-surface crust under the recording sites, yielding reduced amplitude and frequency of the peak ground motion and shifting the apparent corner frequency of the source spectrum to lower values, thereby producing unexpectedly low stress drops.

It is known that various crystalline and liquid compounds form on the downstream surfaces of beryllium windows exposed to air. It is also known that the integrity of such windows may be compromised resulting in leaks through the window. The purpose of this report is to document the occurrences described as they pertain to the NSLS and to analyze, where possible, the various substances formed.

Studies conducted during the 1950s and 1960s of radiation-induced mortality to diverse animal species under various exposure protocols were compiled into a mortality data base. Some 24 variables were extracted and recomputed from each of the published studies, which were collected from a variety of available sources, primarily journal articles. Two features of this compilation effort are (1) an attempt to give an estimate of the uniform dose received by the bone marrow in each treatment so that interspecies differences due to body size were minimized and (2) a recomputation of the LD/sub 50/ where sufficient experimental data are available. Exposure rates varied in magnitude from about 10/sup -2/ to 10/sup 3/ R/min. This report describes the data base, the sources of data, and the data-handling techniques; presents a bibliography of studies compiled; and tabulates data from each study. 103 refs., 44 tabs.

Hypostoichiometric Ni/sub 3/Al alloys of composition 76.2 Ni:23.8 Al containing impurity levels of boron and hafnium were either cold rolled or pressed. Rolled and pressed samples were deformed by 20% and 10% thickness reductions, respectively. Samples were annealed isochronally at approximately 50/sup 0/C intervals up to 1050/sup 0/C. Two major annealing stages were apparent in all three alloys studied. These could be attributed to vacancy migration to sinks and annealing of dislocations and(or) recrystallization. The onset of vacancy migration occurred at approximately 200/sup 0/C in all three alloys. Annealing of dislocations started at 650/sup 0/C to 700/sup 0/C and was complete at 1000/sup 0/C for alloys which contained boron and or hafnium impurities. In the pure alloy the onset of dislocation annealing occurred at 800/sup 0/C and was incomplete at the highest (1050/sup 0/C) annealing temperatures reached.

A calculational thermodynamic equilibrium analysis of the compatibility of ceramic-ceramic composites and a nonequilibrium assessment based on the literature of their use in proposed multimegawatt space nuclear power systems was performed. The five candidate composites included Al/sub 2/O/sub 3/-reinforced Al/sub 2/O/sub 3/, SiC-whisker-toughened Al/sub 2/O/sub 3/, SiC-whisker-toughened Si/sub 3/N/sub 4/, SiC-fiber-reinforced ZrC, and carbon-fiber-reinforced ZrC. The reactor concepts included Brayton cycle (continuous and burst mode) and Rankine cycle. It was determined that Al/sub 2/O/sub 3/-reinforced Al/sub 2/O/sub 3/ and carbon-fiber-reinforced ZrC are compatible in the Brayton-cycle continuous-mode system and that Al/sub 2/O/sub 3/-reinforced Al/sub 2/O/sub 3/, SiC-fiber-reinforced ZrC, and carbon-fiber-reinforced ZrC are compatible in the Rankine-cycle system. None of the candidate ceramic composite systems was likely to be sufficiently stable under Brayton-cycle burst-mode conditions.

To minimize the costs and delivery time delays associated with purchasing type 304L stainless steel materials for service in nitric-acid-containing media, an alternative to the current Oak Ridge Y-12 Plant requirement of testing in accordance with American Society for Testing and Materials (ASTM) A 262, Practice C (the boiling nitric acid test), is being sought. A possible candidate is the electrochemical potentiokinetic reactivation (EPR) test being developed for the nuclear industry and under consideration for acceptance as an ASTM standard. Based on a review of the literature and some limited screening tests, this test, as currently proposed, is not a suitable substitute for the nitric acid test. However, with additional development the EPR test is a likely candidate for providing a quantitative substitute for the current qualitative oxalic acid etching (ASTM A 282, Practice A) often used to accept, but not reject, materials for use in a nitric acid medium.

Experiments in nozzles are extremely important because they provide higher rates of cooling, higher supersaturations and higher nucleation rates than any of the other techniques. Their operating conditions are more typical of the important industrial conditions such as aerodynamic and turbomechanical flows where homogeneous nucleation can have serious consequences. Because the fluid mechanics of nozzles are well defined and understood, nucleation experiments in the nozzle are amenable to sophisticated modeling efforts and much useful insight can be gained regarding the nucleation and droplet growth processes under these severe cooling conditions. This paper summarizes recent experimental work using a gently diverging supersonic Laval nozzle to investigate all three binary pairs in the water-propanol-ethanol ternary system. Of these three binary systems, ethanol-water and propanol-water are both non-ideal and strongly influenced by surface enrichment, while ethanol-propanol should be almost ideal. The authors briefly describe the experimental apparatus and their method for preparing the binary gas mixtures. They present their experimental results and compare them to relevant experimental data and nucleation rate calculations available in the literature.

Biomass is a major, renewable energy resource through out the world, and extensive research is being conducted by many countries on bioenergy technologies. In an effort to improve communications and cooperation in the area of biomass energy, several nations have agreed to a cooperative program of work under the International Energy Agency's Bioenergy Agreement (IEA/BA). Three areas of major importance have been identified including Short Rotation Forestry, Conventional Forestry, and Biomass Conversion. This document describes the 1987 Program of Work for cooperative activities in the area of Biomass Conversion. The background of the cooperation and descriptions of specific conversion projects are presented. Details of activity funding are also provided. 3 tabs.

Drill hole USW G-4 was logged with the US Geological Survey borehole gravity meter (BHGM) BH-6 as part of a detailed study of the lithostratigraphic units penetrated by this hole. Because the BHGM measures a larger volume of rock than the conventional gamma-gamma density tool, it provides an independent and more accurate measurement of the in situ average bulk density of thick lithologic units. USW G-4 is an especially important hole because of its proximity to the proposed exploratory shaft at Yucca Mountain. The BHGM data were reduced to interval densities using a free-air gradient (F) of 0.3083 mGal./m (0.09397 mGal/ft) measured at the drill site. The interval densities were further improved by employing an instrument correction factor of 1.00226. This factor was determined from measurements obtained by taking gravity meter BH-6 over the Charleston Peak calibration loop. The interval density data reported herein, should be helpful for planning the construction of the proposed shaft.

We present predictions for the rapidity and transverse momentum distributions for inclusive production of bottom quarks at SSC energies, pp ..-->.. bX. Our computations are based on the simplest, lowest-order QCD mechanisms. To estimate uncertainties, we use three different choices for structure functions, G(x,Q), as well as different choices for the evolution scale Q.

Fast-neutron multiplication in large PuO/sub 2/ samples has been studied using both Monte Carlo computer codes and the coincidence correlation equations developed by K. Boehnel and N. Ensslin. Samples covering the mass range from 0.1 to 7.2 kg of plutonium have been measured and the multiplication results were compared with the theoretical predictions. The results are in agreement within the uncertainties in the sample characteristics. A parametric study was performed to determine the effect of sample density and moisture variation on the neutron multiplication.

This report represents an analysis of potential enhancement and management options designed to improve instream and riparian zone conditions in the Meyers Cover area of Camas Creek. The efforts expended will contribute to improvement of anadromous species spawning, incubation and rearing habitat. Potential production increases would provide some compensation for hydropower effects in other areas of the Columbia River basin.

This report documents the decay heat, heat transfer, and shielding analyses of the Gesellschaft fuer Nuklear Services (GNS) CASTOR-1C cask used in a spent fuel storage demonstration performed at Preussen Elektra's Wurgassen nuclear power plant. The demonstration was performed between March 1982 and January 1984, and resulted in cask and fuel temperature data and cask exterior surface gamma-ray and neutron radiation dose rate measurements. The purpose of the analyses reported here was to evaluate decay heat, heat transfer, and shielding computer codes. The analyses consisted of (1) performing pre-look predictions (predictions performed before the analysts were provided the test data), (2) comparing ORIGEN2 (decay heat), COBRA-SFS and HYDRA (heat transfer), and QAD and DOT (shielding) results to data, and (3) performing post-test analyses if appropriate. Even though two heat transfer codes were used to predict CASTOR-1C cask test data, no attempt was made to compare the two codes. The codes are being evaluated with other test data (single-assembly data and other cask data), and to compare the codes based on one set of data may be premature and lead to erroneous conclusions.

This report presents work for the feasibility study of central processing of contact-handled TRU waste. Discussion of scenarios, transportation options, summary of cost estimates, and institutional issues are a few of the subjects discussed. (JDL)

The use of perchloroethylene (perc) as an ingredient in coolants for machining enriched uranium at the Oak Ridge Y-12 Plant has been discontinued because of environmental concerns. A new coolant was substituted in December 1985, which consists of an aqueous solution of propylene glycol with borax (sodium tetraborate) added as a nuclear poison and with a nitrite added as a corrosion inhibitor. Uranium surfaces machined using the two coolants were compared with respects to residual contamination, corrosion or corrosion potential, and with the aqueous propylene glycol-borax coolant was found to be better than that of enriched uranium machined with the perc-mineral oil coolant. The boron residues on the final-finished parts machined with the borax-containing coolant were not sufficient to cause problems in further processing. All evidence indicated that the enriched uranium surfaces machined with the borax-containing coolant will be as satisfactory as those machined with the perc coolant.

Laboratory and field leaching experiments are beig conducted by Pacific Northwest Laboratory (PNL) to investigate the performance of solidified low-level nuclear waste in a typical, arid, near-surface disposal site. Under PNL's Special Waste Form Lysimeters-Arid Program, a field test facility was constructed to monitor the leaching of commercial solidified waste. Laboratory experiments were conducted to investigate the leaching and adsorption characteristics of the waste forms in contact with soil. Liquid radioactive wastes solidified in cement, vinyl ester-styrene, and bitumen were obtained from commercial boiling water and pressurized water reactors, and buried in a field leaching facility on the Hanford site in southeastern Washington State. Batch leaching, soil column adsorption, and soil/waste form column experiments were conducted in the laboratory, using small-scale cement waste forms and Hanford site ground water. The purpose of these experiments is to evaluate the ability of laboratory leaching tests to predict leaching under actual field conditions and to determine which mechanisms (i.e., diffusion, solubility, adsorption) actually control the concentration of radionuclides in the soil surrounding the waste form. Chemical and radionuclide analyses performed on samples collected from the field and laboratory experiments indicate strong adsorption of /sup 134,137/Cs and /sup 85/Sr onto the Hanford site sediment. …

Research continued on the chemistry and preparation of bimetallic cyclopentadienyl complexes containing up to two tungsten or one tungsten and a cobalt, rhodium, or ruthenium. The general method for preparation and analysis of polyenes is also discussed. 7 figs., 2 tabs. (CBS)

A continuation of the physical oceanography program to investigate circulation and exchange processes on the South Atlantic Bight (SAB) Continental Shelf is proposed. The transport and dispersal of materials entering the inner shelf zone with river discharge is not well understood at present. Climatological data, satellite imagery, and numerical modeling results indicate two removal routes for these nearshore waters: northeast transport and offshore exchange between Cape Fear and Savannah during the spring and summer when maximum run-off and northward winds prevail; and southward transport and offshore exchange near Cape Canaveral during the fall when southward winds prevail. We have conducted interdisciplinary experiments to investigate the transport processes in the inner to outer shelf between Savannah, Georgia and Cape Fear, North Carolina. In addition we propose to continue synthesis and interpretation of current measurements. The analyses will focus on determining the coupling mechanisms of inner shelf and outer shelf waters with special emphasis placed on resolving the modes and rates of shelf water removal.

This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that predicts temperature and velocity distributions in a wide variety of systems. Through comparisons of code predictions with spent fuel storage system test data, the code's mathematical, physical, and mechanistic models are assessed, and empirical relations defined. The six test cases used to validate the code and code models include single-assembly and multiassembly storage systems under a variety of fill media and system orientations and include unconsolidated and consolidated spent fuel. In its entirety, the test matrix investigates the contributions of convection, conduction, and radiation heat transfer in spent fuel storage systems. To demonstrate the code's performance for a wide variety of storage systems and conditions, comparisons of code predictions with data are made for 14 runs from the experimental data base. The cases selected exercise the important code models and code logic pathways and are representative of the types of simulations required for spent fuel storage system design and licensing safety analyses. For each test, a test description, a summary of the COBRA-SFS computational model, assumptions, …