Themotolerant microalgae were selected from an existing culture collection and isolated from hot spring areas of Yellowstone National Park. Several of them grew at 35 degrees celsius, although only one grew at much better than 1 doubling per day.

This technical memorandum concludes that although the technology is available to create a mediasat system, the high cost and current low demand for remotely sensed data will limit media efforts to own and operate a dedicated remote sensing satellite system.

A computer program has been developed to determine the maximum specific power for prismatic-core reactors as a function of maximum allowable fuel temperature, core pressure drop, and coolant velocity. The prismatic-core reactors consist of hexagonally shaped fuel elements grouped together to form a cylindrically shaped core. A gas coolant flows axially through circular channels within the elements, and the fuel is dispersed within the solid element material either as a composite or in the form of coated pellets. Different coolant, fuel, coating, and element materials can be selected to represent different prismatic-core concepts. The computer program allows the user to divide the core into any arbitrary number of axial levels to account for different axial power shapes. An option in the program allows the automatic determination of the core height that results in the maximum specific power. The results of parametric specific power calculations using this program are presented for various reactor concepts.

This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work.

This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work.

A strong pumping effect has been observed with plasma operation on the toroidal graphite bumper limiter on TFTR. The pumping effect was induced by conditioning the limiter with a short series (10 to 20) of low density deuterium- or helium-initiated discharges. The density decay constant (tau/sub p/*) for gas-fueled ohmic discharges was reduced from tau/sub p/* > 10 s before conditioning to a minimum value of tau/sub p/* = 0.15 s after conditioning, corresponding to a reduction in the global recycling coefficient from approx.100% to less than 50%. Coincident with the low recycling conditions, low current neutral-beam-fueled discharges show global energy confinement times which are enhanced by a factor of two over results with an unconditioned limiter. Two models are proposed for the observed pumping effects: (1) a depletion model based on pumping of hydrogenic species in the near-surface region of the limiter after depletion of the normally saturated surface layer by (carbon and helium) ion-induced desorption; and (2) a codeposition model based on pumping of hydrogenic species in carbon films sputtered from the limiter by the conditioning process.

On the morning of April 10, 1986, the US Department of Energy (DOE) conducted a nuclear weapons effects test, Mighty Oak, 1300 feet below the surface of Rainier Mesa in the T tunnel complex. From the standpoint of containment, there was no accidental release of radioactivity to the atmosphere whatsoever. All radioactivity was contained within the tunnel complex until April 16 when the first controlled purging of the tunnel took place. Mighty Oak purging resulted in a known amount of radioactive noble gases being released in a controlled manner to the atmosphere. The maximum dose any person would have received standing in the open, downwind, for the entire period of purging, would have been 0.27 microrem. From the standpoint of data recovery, Mighty Oak was successful. Approximately 85% of the data from prime test objectives was recovered; however, only 70% of the overall data was recovered. Most equipment - experiment, diagnostic, and construction - within the tunnel complex was lost. This loss occurred as a result of high temperature and radiation. Other passive experiments and data were recovered. Loss of normally recoverable and reusable equipment was approximately 32 million dollars.

A report on analyzes the reasons behind widely divergent estimates of the costs associated with AIDS. Because of the great variation in methods used, the results are not strictly comparable across studies.

Both NRC and EPA regulations require programs of post closure monitoring to detect substantial and detrimental deviations from expected performance. The unexpected in this case would involve anomalous stress changes that might rupture the canisters or changes in the hydrologic regime that might accelerate corrosion. In the event of leakage brought about by any means transport of radionuclides to the accessible environment could occur through unexpected changes in the hydrologic flow regime caused either by the long term effects of the thermal loading by the waste or by changes in regional stress or hydrology. Studies of performance confirmation have identified six parameters or conditions that should be monitored that are associated with the thermal, mechanical and hydrologic phenomena introduced by the waste heat: temperature, stress, displacement, pore pressure, groundwater velocity and permeability. Since it is the thermal load that continues to increase after decommissioning, and which continues to alter the stress field and the hydrological regime, these same six parameters remain the critical ones in post closure monitoring. At two of the repository sites fractures have been clearly shown to be critical in modelling and performance confirmation; at the tuff site fluid saturation is also a critical parameter and for …

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

The development of cryogenic detectors of particles, with emphasis on large mass devices, has been reviewed. Most groups are still tooling up and exploring basic properties of sensors. The main discussion themes are summarized and some of the early experimental results are described.

The objective of this project is the development of a coal water slurry burning residential furnace. A literature survey has been performed. Also, the preliminary testing of prototype components was carried out. Design criteria and specifications are discussed.

Progress is reported on the following: defect formation at the InGaAs/GaAs interface as a function of the misfit parameter, layer thickness, and starting substrate dislocation density; and epitaxial growth on very small islands to verify theoretical predictions of critical layer thickness as a function of area.

We have studied techniques for alignment reticle fabrication. Two design methods are discussed in this report: one uses an iterative procedure and the other uses results from number theory. A third method was also studied briefly; this being a binary chirp grating. Although this was described in a previous report, we did not find it particularly promising and do not discuss it in this document. It is our opinion that either of the two methods discussed in this report can be made into a workable system if there is sufficient interest. It is also our opinion that the reticle design based on number theory, which uses the polarization encoding of two patterns onto a single substrate, is a powerful method which deserves further consideration.

The ever increasing complexity of nuclear physics experiments places severe demands on computerized data acquisition systems. A natural evolution of these systems, taking advantages of the independent nature of ''events,'' is to use identical parallel microcomputers in a front end to simultaneously analyze separate events. Such a system has been developed at Argonne to serve the needs of the experimental program of ATLAS, a new superconducting heavy-ion accelerator and other on-going research. Using microcomputers based on the National Semiconductor 32016 microprocessor housed in a Multibus I cage, CPU power equivalent to several VAXs is obtained at a fraction of the cost of one VAX. The front end interfacs to a VAX 11/750 on which an extensive user friendly command language based on DCL resides. The whole system, known as DAPHNE, also provides the means to reply data using the same command language. Design concepts, data structures, performance, and experience to data are discussed.

Safety analyses of nuclear reactors require information about the loss of fuel which may occur at high temperatures. In this study, the surface of a uranium dioxide target was heated rapidly by a laser. The uranium surface was vaporized into a vacuum. The uranium bearing species condensed on a graphite disk placed in the pathway of the expanding uranium vapor. Scanning electron microscopy and X-ray analysis showed very little droplet ejection directly from the laser target surface. Neutron activation analysis was used to measure the amount of uranium deposited. The surface temperature was measured by a fast-response automatic optical pyrometer. The maximum surface temperature ranged from 2400 to 3700/sup 0/K. The Hertz-Langmuir formula, in conjunction with the measured surface temperature transient, was used to calculate the theoretical amount of uranium deposited. There was good agreement between theory and experiment above the melting point of 3120/sup 0/K. Below the melting point much more uranium was collected than was expected theoretically. This was attributed to oxidation of the surface. 29 refs., 16 figs., 7 tabs.

This dissertation is about nuclear magnetic resonance (NMR) spectroscopy in the absence of applied magnetic fields. NMR is usually done in large magnetic fields, often as large as can be practically attained. The motivation for going the opposite way, toward zero field, is that for certain types of materials, particularly powdered or polycrystalline solids, the NMR spectra in zero field are easier to interpret than those obtained in high field. 92 refs., 60 figs., 1 tab.

Bombardment of thick Be-metal targets with several-MeV deuterons produces continuum-neutron fields which offer considerable potential for the development and validation of neutron-reaction cross sections. A facility based on this concept has been installed at the Argonne National Laboratory FNG accelerator. A description is provided of this facility and of the research studies which have been initiated to exploit its capabilities. Some technical considerations in the utilization of accelerator-produced continuum-neutron fields for reaction cross-section investigations are discussed. Results from several recent neutron-spectrum and integral cross-section measurements are presented, and the implications are reviewed. 13 refs., 8 figs.

Newsletter issued by the Texas Division of Emergency Management discussing news, events, statistics, and other relevant information related to the agency and preparedness in Texas.

The Department of Energy Radiological Calibration Intercomparison Program was initiated in January 1986, under the research portion of the DOE Laboratory Accreditation Program. The program operates via the exchange of transfer standards, consisting of instrument sets and standard secondary beta sources. There are two instrument sets and the scheduled use has been staggered such that one set is available for use during each month. One set of secondary standard beta sources is available for use bimonthly. During the 1986 fiscal year, five laboratories used the instrument sets and three laboratories used the beta source set. Results were reported for all the measurements. The average and one standard deviation of the ratios of participant results to Pacific Northwest Laboratory calibration values were 1.12 +- 0.17 for gamma measurements. Those ratios for the gamma measurements varied from 0.98 to 3.06. The larger differences of results from measurements performed at two facilities were directly attributable to unfamiliarity with the intercomparison instruments. The average and one standard deviation of the ratios of participant results to PNL calibration values obtained using the secondary /sup 90/Sr beta source was 1.02 +- 0.05, which is well within measurement uncertainties. The one participant who performed measurements using /sup …

Two line ratios, the forbidden line at 845.5 A (2s/sup 2/2p /sup 2/P/sub 1/2/ - 2s/sup 2/2p /sup 2/P/sub 3/2/) to the allowed line at 135.7 A (2s/sup 2/2p /sup 2/P/sub 1/2/ - 2s2p/sup 2/ /sup 2/D/sub 3/2/) in Fe XXII and the forbidden line at 592.1 A (2s/sup 2/2p/sup 4/ /sup 3/P/sub 2/ - 2s/sup 2/2p/sup 4/ /sup 1/D/sub 2/) to the forbidden line at 1118.2 A (2s/sup 2/2p/sup 4/ /sup 3/P/sub 2/ - 2s/sup 2/2p/sup 4/ /sup 3/P/sub 1/) in Fe XIX, have been measured as the ion temperature-sensitive line ratios during rf heating in the Princeton Large Torus. The results indicate that deuteron collisions in plasmas of high deuteron temperature have a noticeable effect on the intensity of the forbidden lines. Measured relative intensities are compared with values from level population calculations, which include deuteron collisional excitation between the levels of the ground configuration. The agreement between the observed and calculated ratios is within 30%. A method for deuteron (or proton) temperature measurement in tokamak plasmas is discussed. 37 refs.

It is shown that increasing additions of Dy causes the remanence B/sub r/ to decrease linearly. The intrinsic coercivity, iHc, increases sharply for small additions of Dy, but the increase is not proportional for higher Dy contents. The iHc increases almost linearly with the effective anisotropy field of the RE/sub 2/Fe/sub 14/B phase until the Dy content is about 10% of the total rare earth content. Above this concentration, there is strong deviation from linearity. Various types of possible concentration profiles of the substituted rare earth are suggested. It is also argued that preferential segregation of Dy to the interfaces could be beneficial in increasing the nucleation field. Morphologically there is no apparent effect of Dy on the microstructure. However, in the 5 atomic % Dy sample, Dy rich oxides were observed. It is shown through Energy Dispersive Xray Spectroscopy (EDXS) line profiling that Dy partitions preferentially into the RE/sub 2/Fe/sub 14/B phase in all the cases. No segregation of Dy to the interphase interfaces has been detected.

In the present report, the effects of both static and diffusing impurities on domain growth kinetics are considered. In particular, the Monte Carlo simulations for nonconservative (Glauber) dynamics are employed to examine the effects of quenched impurities on domain growth in the Potts model with varying degeneracy Q (2 less than or equal to Q less than or equal to 48). The effects of diffusing impurities are examined within the framework of the Ising model (i.e., Potts model with Q = 2) as a function of impurity diffusivity. Finally, a theoretical analysis of the diffusing-impurity results is presented.

Many corrosion processes of interest to the nuclear power industry occur in high-temperature/high-pressure aqueous systems. The investigation of the kinetics of the appropriate electrode reactions is a serious experimental challenge, partially because of the high temperatures and pressures and partially because many of these reactions are very rapid, requiring fast relaxation measurements. An electrochemical measuring system is described which is suitable for measurements of the kinetics of fast electrode reactions at temperatures extending to at least 300C and pressures to at least 10 MPa (100 atmospheres). The system includes solution preparation and handling equipment, the electrochemical cell, and several electrode designs. One of the new designs is a coaxial working electrode-counter electrode assembly; this electrode can be used with very fast-rising pulses, and it provides a well defined, repeatedly-polishable working surface. Low-impedance reference electrodes are also described, based on electrode concepts responding to the pH or the redox potential of the test solution. Additionally, a novel, long-life primary reference electrode design is reported, based on a modification of the external, pressure-balanced Ag/AgCl reference electrode.