Recent results on hadronic D/sub s/ and D decays from the Mark III collaboration are presented. The absolute branching ratio B(D/sub s//sup +/ /yields/ /phi//pi//sup +/) is studied by searching for fully reconstructed e/sup +/e/sup /minus// /yields/ D/sub s/*/sup /plus minus//D/sub s//sup /minus plus// events using seven hadronic decay modes of the D/sub s//sup +/. A limit of B(D/sub s//sup +/ /yields/ /phi//pi//sup +/) < 4.1% at 90% C.L. is obtained. Evidence is presented for the decay D/sub s//sup +/ /yields/ f/sub 0/(975)/pi//sup +/ which agrees with a recent experimental observation. Upper limits are set for the relative branching ratios B(D/sub s//sup +/ /yields/ /eta//pi//sup +/)/B(D/sub s//sup +/ /yields/ /phi//pi//sup +/) < 2.5 and B(D/sub s//sup +/ /yields/ /eta//prime//pi//sup +/)/B(D/sub s//sup +/ /yields/ /phi//pi//sup +/) < 1.9, where the /eta/ is studied in both the /gamma//gamma/ and the /pi//sup +//pi//sup /minus///pi//sup 0/ decay modes and the /eta//prime/ in the /eta//pi//sup +//pi//sup /minus//, /eta/ /yields/ /gamma//gamma/ decay chain. The resonant substructure of D/sup 0/ /yields/ K/sup /minus///pi//sup +//pi//sup /minus///pi//sup +/ and D/sup +/ /yields/ /bar K//sup 0//pi//sup +//pi//sup /minus///pi//sup +/ is studied. The branching ratio of D/sup 0/ /yields/ /bar K/*/sup 0//rho//sup 0/ is found to be smaller than the theoretically …

This document discusses a support provided for use in a thermionic converter to support an end of an emitter to keep it out of contact with a surrounding collector while allowing the emitter end to move axially as its temperature changes. The emitter end is supported by a spring structure that includes a pair of Belleville springs, and the spring structure is supported by a support structure fixed to the housing that includes the collector. The support structure is in the form of a sandwich with a small metal spring-engaging element at the front end, a larger metal main support at the rear end that is attached to the housing, and with a ceramic layer between them that is bonded by hot isostatic pressing to the metal element and metal main support. The spring structure can include a loose wafer captured between the Belleville springs. 7 figs.

Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including applied physical chemistry, separation science and technology, and high level waste and repository interactions.

This feasibility study resulted in verification of a direct and two alternate indirect techniques for making in-situ determinations of {sup 90}Sr and other radionuclide levels in a Hanford facility to be decommissioned that was evaluated using the Allowable Residual Contamination Level (ARCL) method. The ARCL method is used to determine the extent of decontamination that will be required before a facility can be decommissioned. A sump in the 1608F Building was chosen for the feasibility study. Hanford decommissioning personnel had previously taken 79 concrete and surface scale samples from the building to be analyzed by radiochemical analysis. The results of the radiochemical analyses compare favorably with the values derived by the in-situ methods presented in this report. Results obtained using a portable spectrometer and thermoluminescent dosimeters (TLDs) were both very close to the radiochemistry results. Surface {sup 90}Sr levels detected on the sump floor were 550 pCi/cm{sup 2} using the spectrometer system and 780 pCi/cm{sup 2} using the TLD data. This compares favorably with the levels determined by radiochemical analyses (i.e., 230 to 730 pCi/cm{sup 2}). Surface {sup 90}Sr levels detected on the sump wall ranged between 10 and 80 pCi/cm{sup 2} using the spectrometer system, compared with a conservative …

Following removal of Cs-137 by ion exchange in the Supernatant Treatment System immediately upstream, the radioactive liquid waste is volume-reduced by evaporation. Trace amounts of Cs-137 in the resulting distillate are removed by ion exchange, then the distillate is discharged to the existing plant water treatment system. The concentrated product, 37 to 41 percent solids (by weight), is encapsulated in cement, producing a stable low-level waste form. This report provides a summary of work performed to test the Liquid Waste Treatment System following construction turnover and prior to radioactive operation. All mechanical and electrical components, piping, valves, pumps, tanks, controls, and instrumentation required to operate the system were tested; first with water, then with simulated waste. Subsystems (individual tanks, pumps, and control loops) were tested individually, then as a complete system. Finally, the system began a controlled start-up phase, which included the first four months of radioactive operation. Components were tested for operability then for performance data to verify the system`s ability to produce an acceptable waste form at design feed rates.

Conceptual designs for waste packages containing spent fuel or high-level waste glass have been developed for use in a repository at Yucca Mountain. The basis for these designs reflects the unique nature of the expected service environment associated with disposal in welded tuff in the unsaturated zone. In addition to a set of reference designs, alternative design concepts are being considered that would contain and isolate the waste radionuclides in a more aggressive service environment. Consideration is also being given to the feasibility of a concept known as ``heat tailoring`` that employs the thermal energy released by the wasteforms to enhance and extend the performance of the containers. 5 refs., 3 figs.

During the report period, work continued on the life-cycle testing, optimization and refining of the second-generation furnace assembly, which comprises all the major furnace components: The combustor, heat exchanger, and baghouse, as well as the auxiliary subsystems. The furnace has operated for about 90 hours, and has burned 1,000 pounds of CWS. During testing, the only maintenance that was performed on the system was to clean the bag filters to obtain ash samples for analysts. Concurrent with testing the second-generation furnace, fabrication and assembly of the third-generation furnace was completed, and a life-cycle testing and optimization process for this furnace has started. In contrast to the second-generation furnace, which was designed more as an experimental unit, the third-generation furnace is a stand-alone heating unit Incorporating the standard air handling system, blower, pump, and control box as part of the furnace. During the report period, the third-generation furnace operated for a total of 35 hours, and burned more than 300 pounds of CWS, with average tests lasting 6 hours. During the next quarter, life-cycle testing of the third-generation furnace will continue to identify areas needing further development.

During the report period, work continued on the life-cycle testing, optimization and refining of the second-generation furnace assembly, which comprises all the major furnace components: The combustor, heat exchanger, and baghouse, as well as the auxiliary subsystems. The furnace has operated for about 90 hours, and has burned 1,000 pounds of CWS. During testing, the only maintenance that was performed on the system was to clean the bag filters to obtain ash samples for analysts. Concurrent with testing the second-generation furnace, fabrication and assembly of the third-generation furnace was completed, and a life-cycle testing and optimization process for this furnace has started. In contrast to the second-generation furnace, which was designed more as an experimental unit, the third-generation furnace is a stand-alone heating unit Incorporating the standard air handling system, blower, pump, and control box as part of the furnace. During the report period, the third-generation furnace operated for a total of 35 hours, and burned more than 300 pounds of CWS, with average tests lasting 6 hours. During the next quarter, life-cycle testing of the third-generation furnace will continue to identify areas needing further development.

Samples of two titanium alloys, Ti-6A1-4V and Ti-15V-3Cr-3Sn-3A1, were ion implanted with a combination of nitrogen (N+) and oxygen (O+). For each alloy, implantation parameters were chosen to give implanted nitrogen concentrations of approximately 10 or 50 atomic percent, from a depth of 100 nanometers to a depth of 400 nanometers. In all but one case, dual energy (200 keV and 90 keV) implantations of nitrogen were used to give a relatively uniform nitrogen concentration to a depth of 300 nanometers. In each case, oxygen was implanted at 35 keV, following the nitrogen implantation, to give an oxygen-enriched region near the surface. The implanted samples were then examined by Auger electron spectroscopy (AES) combined with argon ion sputtering. In order to determine the stoichiometry of the nitrogen implanted regions, it was necessary to determine the N (KVV) contribution to the overlapping N (KVV) and Ti (LMM) Auger transitions. It was also necessary to correct for the ion-bombardment-induced compositional changes which have been described in an earlier study of titanium nitride thin films. The corrected AES depth profiles were in good agreement with theoretical predictions.

The procedure was designed for the simple, rapid determination of the Fe(II)/Fe(III) ratio in glass samples. The procedure consists of the following steps: dissolution of the pulverized glass sample in a sulfuric-hydrofluoric acid mixture, containing ammonium vanadate, which preserves the Fe(II) content; addition of boric acid to destroy iron-fluoride complexes, making the iron available for color formation with Ferrozine; addition of pH 5 buffer and Ferrozine reagent to form the magenta-colored ferrous-Ferrozine complex, with measurement of the absorbance for the determination of Fe(II) content; and, addition of ascorbic acid to reduce Fe(III) to Fe(II), with a second absorbance measurement that determines total Fe. Directions for the preparation of glass from non-radioactive sludge samples are provided. The analysis of this prepared glass for the Fe(II)/Fe(III) ratio is an indication of the ratio that would be in a plant batch of glass if made from this sludge.

At the present time, there are no binding rules of evidence or set of evidentiary principles to be applied in Senate impeachment trials. Rather, recourse is taken to the evidentiary rules and principles applicable in contemporaneous court proceedings and to precedents from past impeachment trial to provide guidance for Senate Impeachment Trial Committees or for the full Senate on evidentiary questions which arise in the impeachment context. This report compiles evidentiary precedents from the Senate impeachment trials of Judges Harry E. Claiborne, Halsted Ritter, Harold Louderback, and Charles Swayne. The evidentiary rulings and principles gleaned from this examination are arranged in subject matter categories, and within those categories, in reverse chronological order by trial.

An overview is given of atomic physics issues which have been studied on tokamaks with the help resolution x-ray spectroscopy. The issues include the testing of model calculations predicting the excitation of line radiation, the determination of rate coefficients, and accurate atomic structure measurements. Recent research has focussed primarily on highly charged heliumlike (22 less than or equal to Z less than or equal to 28) and neonlike (34 less than or equal to Z less than or equal to 63) ions, and results are presented from measurements on the PLT and TFTR tokamaks. Many of the measurements have been aided by improved instrumental design and new measuring techniques. Remarkable agreement has been found between measurements and theory in most cases. However, in this review those areas are stressed where agreement is worst and where further investigations are needed. 19 refs., 13 figs., 2 tabs.

A brief description is given of the SLD calorimeter system, with emphasis on the iron calorimeter/muon identifier. Design choices and expected performance are summarized. 6 refs., 8 figs.

The group considered physics, accelerator, and polarized source issues. Most of the physics study was concerned with what significant and unique experiments could be done if polarized protons could be accelerated in the main injector and eventually in the Tevatron. 12 refs., 4 figs.

This very significant and useful report assessed state-of-the-art geothermal technologies. The findings presented in this report are the result of site visits and interviews with plant owners and operators, representatives of major financial institutions, utilities involved with geothermal power purchases and/or wheeling. Information so obtained was supported by literature research and data supplied by engineering firms who have been involved with designing and/or construction of a majority of the plants visited. The interviews were conducted by representatives of the Bonneville Power Administration, the Washington State Energy Office, and the Oregon Department of Energy during the period 1986-1989. [DJE-2005]

This report presents an analysis of the in-situ geomechanical testing needs for the Exploratory Shaft (ES) test facility at the Yucca Mountain site in Nevada. The testing needs are derived from 10CFR60 regulations and simple thermomechanical canister- and room-scale numerical studies. The testing approach suggested is based on an ``iterative`` procedure of full-scale testing combined with numerical and empirical modeling. The testing suggested is based heavily on demonstration of excavation and thermal loading of full-scale repository excavations. Numerical and/or empirical models are compared to the full-scale response, allowing for adjustment of the model and evaluation of confidence in their predictive ability. Additional testing may be specified if confidence in prediction of the rock mass response is low. It is suggested that extensive drifting be conducted within the proposed repository area, including exploration of the bounding Drill Hole Wash and Imbricate fault structures, as well as the Ghost Dance fault. This approach is opposed to an a priori statistical specification of a number of ``point`` tests which attempt to measure a given property at a specific location. 40 refs., 49 figs., 6 tabs.

The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG models. The models are those used by General Atomics (GA) and by the German Nuclear Research Center at Juelich (KFA/ISF). A benchmark calculation was performed for fuel temperatures predicted for the US Department of Energy sponsored Modular High Temperature Gas Cooled Reactor (MHTGR). Good agreement in the benchmark calculations supports the on-going efforts to verify and validate the independently developed codes of GA and KFA/ISF. This work was performed under the US/FRG Umbrella Agreement for Cooperation on Gas Cooled Reactor Development. 6 refs., 3 figs., 3 tabs.

We consider a class of problems, notably double ionization, which require accurate descriptions of correlation in both the initial and final states. Methods are presented for representing correlated wavefunctions on a basis spline lattice, and for calculating bound-continuum transition probabilities. 13 refs.

The electron beam in the XLS will collide with the residual gas in the vacuum chamber. The positive ions will be trapped in the potential well of the electron beam. They will perform stable or unstable oscillations around the beam under the repetitive Coulomb force of the bunches. If not cleared, the captured ions will lead to partial or total neutralization of the beam, causing both, a decrease of life-time and a change in the vertical tunes as well as an increase in the tune-spread. They can also cause coherent transverse instabilities. The degree of neutralization {theta} that one can tolerate, is primarily determined by the allowable tune shift, which of the XLS is between 1 and 5 10{sup {minus}3}. Electrostatic clearing electrodes will be used to keep the neutralization below the desired limit. In order to determine their location and the necessary clearing-rate and voltage, we examine the ion production rate, longitudinal velocity of ions in field-free regions and in the dipoles to see what distance the ions can travel without clearing before the neutralization of the beam reaches the prescribed limit, beam potential to see the locations of the potential wells, voltage requirements for ion clearing, critical mass …

Sputtering erosion of the proposed ITER divertor has been analyzed using the REDEP computer code. A carbon coated plate at medium and low plasma edge temperatures, as well as beryllium and tungsten plates, have been examined. Peak net erosion rates for C and Be are very high (/approximately/20--80 cm/burn/center dot/yr) though an order of magnitude less than the gross rates. Tritium buildup rates in codeposited carbon surface layers may also be high (/approximately/50--250 kg/burn/center dot/yr). Plasma contamination, however, from divertor sputtering is low (/approx lt/.5%). Operation with low Z divertor plates, at high duty factors, therefore appears unacceptable due to erosion, but may work for low duty factor (/approximately/2%) ''physics phase'' operation. Sweeping of the poloidal field lines at the divertor can reduce erosion, by typical factors of /approximately/2--8. A tungsten coated plate works well, from the erosion standpoint, for plasma plate temperatures of /approximately/40 eV or less. 18 refs., 11 figs., 3 tabs.

We report on the development of a new polystyrene based plastic scintillator. Optical absorption, fluorescence and light output measurements are presented. Preliminary results of radiation damage effects are also given and compared to the effects on a commercial plastic scintillator, NE 110. 6 refs., 12 figs.

We describe an ultra-high density scintillating fiber and tungsten calorimeter used as an active beam-dump for electrons. Data showing the calorimeter response to electrons with momenta between 50 and 350 GeV/c are presented. 9 figs.

The consequences of simulating nuclear reactor loss of coolant accident (LOCA) radiation effects with Cobalt-60 gamma ray irradiators have been investigated. Based on radiation induced damage in polymer base materials, it was demonstrated that electron/photon induced radiation damage could be related on the basis of average absorbed radiation dose. This result was used to estimate the relative effectiveness of the mixed beta/gamma LOCA and Cobalt-60 radiation environments to damage both bare and jacketed polymer base electrical insulation materials. From the results obtained, it is concluded that present simulation techniques are a conservative method for simulating LOCA radiation effects and that the practices have probably substantially overstressed both bare and jacketed materials during qualification testing. 9 refs., 8 figs., 5 tabs.

A proof-of-concept study for a novel shale oil refining process was undertaken. This project promises reduced upgrading costs, thereby making shale oil development more feasible for commercialization. The process consists of distillation of raw shale oil into a distillate and residue portion, cracking of the residue by hydropyrolysis, and selective hydrotreating of narrow boiling cuts from the total distillate. Based on models and experimental data, the end product slate is projected to be 34% naphtha, 57% middle distillate, and 10.3% atm residue + coke. Hydrogen addition is 1.3% or 800 scf/bbl. These results are considerably improved over conventional processing, which gives 14% naphtha, 41% middle distillate, and 48.2% residue + coke and hydrogen addition of 3.2% or 2000 scf/bbl. More quantitative data and preliminary economics will be obtained in the next phase of study. 13 refs., 3 figs., 6 tabs.