The prediction of future CO/sub 2/ content in the atmosphere is not completely credible because the oceanographers and terrestrial ecologists do not agree on the global CO/sub 2/ balance. Very precise measurements of O/sub 2//N/sub 2/ ratio using Raman scattering over a few years' period could provide important information and lead to the explanation of the disparity in the atmospheric CO/sub 2/ balance. An optical discriminator-counter has been developed to count closely spaced optical events in the few photon level. Simulated optical events as close as 2.5 ns apart had been positively detected by using selected photomultipliers and optimized discriminators. Testing of the optical discriminator-counter was done by using an electrical pulse pair spaced 3 ns apart and also by a similar optical pulse pair generated by fast light-emitting diode. The photomultiplier is capable of counting an average single photoelectron pulse frequency of 50 MHz and has a sensitive detecting area of 50 mm in diameter. The discriminator performance is discussed.

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.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) investigating alternative concepts for components of molten carbonate fuel cell stacks and (2) improving our understanding of component behavior.

The primary objective of this work was to demonstrate that copper silver selenide and TAGS could be segmented. The hot junction temperature was planned to be 725/sup 0/C with the segmentation temperature at 400/sup 0/C, both temperatures were selected to prevent excessive sublimation from the hot ends of the segments, respectively. The program was planned as a cooperative effort between General Atomic company and Teledyne Energy Systems. Accordingly, General Atomic synthesized the CuAgSe that was used to fabricate the test hardware that was ultimately delivered to General Atomic for testing. Both the CuAgSe and TAGS were hot pressed in an argon atmosphere then the segments were furnace-bonded to each other. A secondary objective was to produce CuAgSe powder by rapid solidification.

Final report analyzing aerial gamma ray and magnetic data in the Columbus quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

Final report analyzing aerial gamma ray and magnetic data in the Detroit quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

Final report analyzing aerial gamma ray and magnetic data in the Manitowoc and Traverse City quadrangles, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

Final report analyzing aerial gamma ray and magnetic data in the Milwaukee and Midland quadrangles, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

Final report analyzing aerial gamma ray and magnetic data in the Racine and Grand Rapids quadrangles, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

Final report analyzing aerial gamma ray and magnetic data in the Tawas City and Flint quadrangles, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.

To assist the Department of Energy in its investigation of methods for recycling used motor oil, Market Facts conducted a telephone survey of individuals who change their own motor oil. The study examined the amount of oil used, oil change practices, oil disposal methods, and perceptions and attitudes toward used motor oil disposal and oil recycling. The results of this survey are presented in this report. The findings of this study confirm the generally held view that about half the vehicle households in the United States now do their own oil changes and additions. These do-it-yourselfers (DIY) households account for almost two-thirds of the motor oil consumed by all US households and produce about one-third of one billion gallons of used motor oil annually. At least half of this used motor oil, more than 170 million gallons, is returned to the environment in a form that pollutes the ground and endangers the water supply. Measures such as requiring information about proper disposal and the need for recycling used oil to be printed on motor oil containers have been taken in many states. The need for reminder advertising and reinforcement education and information and practical measures to ease the burden of …

Three standard reference materials, flyash, soil, and ASI 4340 steel, were analyzed by a method of absolute instrumental neutron activation analysis (INAA). Two different light water pool-type reactors were used to produce equivalent analytical results even though the epithermal to thermal flux ratio in one reactor was higher than that in the other by a factor of two.

This report evaluates the risks involved with shipping uranium ore concentrates by truck in an attempt to provide some perspective on the system safety issues. The basic probabilistic risk evaluation methodology used in this study is similar to that employed by Pacific Northwest Laboratory (PNL) in a series of risk analyses on the transportation of potentially hazardous energy materials. The risk model has been constructed as a series of separate analysis steps to allow the system risk to be readily reevaluated as additional data become available or as postulated system characteristics change. The reslts of this analysis show that the risks to the public health and safety from yellowcake releases during a transportation accident are insignificant. Accidents involving truck shipments of yellowcake are expected to occur at a rate of about ten a year. However, only one-fifth of these accidents, or about two a year, are expected to cause a release of yellowcake to the environment. None of these accidents was estimated to produce any potential fatalities. The low concentration of radioactivity distributed throughout the material resulted in no significant increase in radiation doses above normal background levels to members of the general public.

The case is considered in which the blanket product stream has been purified to the point where only protium, tritium, and a small quantity of deuterium remain. A cryogenic distillation cascade concept developed specifically to handle this enrichment problem is shown. The concept is based on a series of distillation columns and equilibrators capable of producing a protium-rich stream containing less than 1000 appm T and a tritium-rich stream containing less than 2000 appm H. It is envisioned that both of these streams could be blended with streams of comparable composition in the mainstream position of the fuel cycle without further processing. The computational analysis of the cascade was based on a fixed arrangement of columns and equilibrators and a fixed number of theoretical plates per columns, since these features are less easily varied in an actual system than reflux ratios and flow rates. In order to test the flexibility of this conceptual enruchment system to adjust to variations of the H/T ratio in the feed, H/T values of 0.333, 1.00, and 3.00 were investigated.

A technique for performing calculationally assisted evaluations of shift-register coincidence counter data is discussed. An example of a typical application for some high mass PuO/sub 2/ samples is presented. Methods for applying the technique to general coincidence counter use are described.

The local stability of the EBT plasma is analyzed for the long wavelength perturbations in the frequency regime, ..omega.. approx. less than or equal to ..cap omega../sub i/(..cap omega../sub i/ is ion cyclotron frequency). In addition to the low frequency interchange instability, the plasma can be unstable to the compressional Alfven wave. Contrary to the previously obtained quadratic dispersion relation in ..omega.. for the interchange mode, our dispersion relations for both types of instabilities are cubic in ..omega... New stability boundaries are found, for the hot electron interchange mode, to relate to the enhanced compressibility of the core plasma in the presence of hot electrons. The compressional Alfven instability is driven due to the coupling of hot electron magnetic drifts and diamagnetic drift with the compressional Alfven wave. The stability conditions of these two types of instabilities are opposite to each other.

A single-mode, nonlinear analysis of the 2XIIB experimental results is under development. A Model-I (infinite geometry, no mirror losses or source beams) analysis is nearly complete. Model II (mirror losses, beams, energy drag) is in progress. Nonlinear analysis of the 2..omega../sub p/ instability near the quarter-critical point in an inhomogeneous plasma is continuing.

Two sets of parameters have been developed to study stochastic accumulation. The question arises of the size of the transverse emittance required to achieve an antiproton yield of 1.2 x 10{sup 8} {bar p}'s/MR cyc1e for 4.5 GeV and 8 GeV {bar p} kinetic energies, given a full momentum acceptance of 4%. The results quoted in the paper are obtained with a Monte Carlo program which uses a fit to the {bar p} production invariant cross section that has been presented previously. An article describing the program is in preparation.

Bent cylindrical mirrors are considered as substitutes for paraboloidal and ellipsoidal mirrors in x-ray beamlines. Analytic and raytracing studies are used to compare their optical performance with the corresponding ideal elements. Particular emphasis is placed on obtaining the practical limitations in the application of bent cylinders to typical beamline configurations.

Activities of the Los Alamos Nuclear Data Group for January 1 through March 31, 1981, are described. Topics include: (1) peripheral effects in R-matrix theory; (2) Coulomb corrections in light nuclei; (3) new R-matrix analysis of reactions in the /sup 7/Li system; (4) variance-covariance analysis of n + Li reactions; (5) calculated charged-particle emission in the mass-90 region; (6) determination of deformed optical model parameters for neutron reactions on /sup 235/U and /sup 239/Pu; (7) calculation of excited state cross sections for actinide nuclei; (8) calculation of the prompt neutron spectrum and ..nu../sub p/ for the spontaneous fission of /sup 252/Cf; (9) international nuclear model codes comparison study; (10) an improved calculation of heating and radiation damage from neutron capture; (11) LMFBR cross-section production with MAX; (12) TRANSX development; (13) THOR calculations; (14) covariance processing; (15) analysis of charges for use of central computing facility; (16) S/sub n/ calculations for D/sub 2/O sphere; (17) integral data testing of ENDF/B fission-product data; (18) decay power comparisons using ENDF/B-IV and -V data in CINDER-10; (19) ENDF/B-V data testing and summary data; (20) SPEC5: code to produce multigroup spectra; and (21) calculation of H. B. Robinson-2 fuel isotopics and comparison with measurements. (WHK)

Verification of the regional wind energy resource assessments produced by the Pacific Northwest Laboratory addresses the question: Is the magnitude of the resource given in the assessments truly representative of the area of interest. Approaches using qualitative indicators of wind speed (tree deformation, eolian features), old and new data of opportunity not at sites specifically chosen for their exposure to the wind, and data by design from locations specifically selected to be good wind sites are described. Data requirements and evaluation procedures for verifying the resource are discussed.

Reconstruction of the radial two-dimensional distributions of fission products using projections obtained by nondestructive gamma scanning was evaluated. The filtered backprojection algorithm provided the best reconstruction for simulated gamma-ray sources, as well as for actual irradiated fuel material. Both a low-burnup (11.5 GWd/tU) light-water reactor fuel rod and a high-burnup (179.1 GWd/tU) fast breeder reactor fuel rod were examined using this technique.

The actinide concentrations of the defense transuranic (TRU) wastes were analyzed and the potential effects of the radiation on the properties of the wastes after conversion to immobile forms were assessed. The study focused on the contact-handled retrievably-stored wastes. The major components of the current inventory are defense plutonium-contaminated wastes containing various amounts of /sup 241/Am. The wastes stored at Idaho National Engineering Laboratory (INEL) are typical of the wastes in this category. There is also a substantial amount of wastes contaminated with plutonium enriched in /sup 238/Pu arising from the Department of Energy's isotopic heat-source programs. Most of these wastes are stored at the Los Alamos National Laboratory (LANL) and the Savannah River Plant (SRP) sites. Four reference wastes were selected representing a credible range of actinide activities and were used for estimating radiation doses to the final waste forms based on: INEL first stage sludge, a composite of all wastes at INEL, a composite of all wastes at LANL including both defense and heat source plutonium wastes, and a composite of all heat-source plutonium wastes at SRP free from defense plutonium. From integrated alpha and beta-gamma doses over a 10/sup 5/y storage period, it is concluded that: accumulated …

The COBRA/CFTL code has been developed by Oak Ridge National Laboratory (ORNL) for thermal-hydraulic analysis of simulated gas-cooled fast breeder reactor (GCFR) core assemblies to be tested in the core flow test loop (CFTL). The COBRA/CFTL code was obtained by modifying the General Atomic code COBRA*GCFR. This report discusses these modifications, compares the two code results for three cases which represent conditions from fully rough turbulent flow to laminar flow. Case 1 represented fully rough turbulent flow in the bundle. Cases 2 and 3 represented laminar and transition flow regimes. The required input for the COBRA/CFTL code, a sample problem input/output and the code listing are included in the Appendices.