Concerned with Taiwan's growing assertiveness in world affairs, symbolized recently by Taiwan President Lee Teng-hui's June 1995 visit to the United States, Beijing has shifted to a harder line toward Taiwan.

U.S. policymakers face continued debate over normalizing U.S. relations with Vietnam. Some favor greater U.S. flexibility and forward movement in relations with Vietnam; others oppose such changes until Vietnam meets long-standing U.S. conditions, especially accounting more fully for U.S. prisoners of war/missing in action (POW/MIA) from the Vietnam War.

This report discusses congressional interest in the leadership change and economic transformation underway in China, which has grown substantially over the past two years. Leading congressional concerns focus on how economic conditions in China pose opportunities for U.S. enterprise and how the evolution of conditions in China foster U.S. security, economic, and political interests. Congressional concern with China grew in 1995 as a result of reports of the serious decline in the health of senior Chinese leader Deng Xiaoping.

U.S. policy concerns Taiwan center on striking a proper balance between increasing ties with the People's Republic of China (PRC) while sustaining support for Taiwan. Despite eased tensions in the Taiwan Strait and extensive Taiwan trade with and investment in the China mainland, the two sides remain politically far apart and compete for international influence.

Further investigations of assisted pyrolysis by the addition of ethane as a free-radical initiator were carried out during this reporting period. The effects of temperature, space velocity, and ethane/methane ratio, in the presence of quench water, have been addressed. As expected, reaction quenching resulted in lower conversions than without quenching, but also in significantly lower yields of {open_quotes}tar-like{close_quotes} products. High C{sub 2}/C{sub 1} ratios and low space velocities result in significant increases in the {open_quotes}tar-like{close_quotes} product yields. Very low ethane concentrations were required to initiate methane pyrolysis at lower temperatures without a major negative effect on product selectivities.

The Department and its contractors have participated in at least six reviews since 1991 encompassing aspects of subsidies at the test site. Several of these reviews resulted in reports recommending reductions to the housing, food, and bus services. A strategic planning report completed in November 1994, for example, recommended closing certain food service facilities, increasing housing rates to fair market value, and studying a bus depot system. Other reports echoed the same themes. The Department should be credited for recognizing that actions should be taken to reduce subsidy costs. Moreover, the Acting Manager, Nevada Operations office, has been proactive in reducing the busing subsidy by decreasing the number of buses and bus routes. The Acting Manager has also been fully supportive of the effort to further reduce subsidies. We appreciate these efforts.

A finite element transport model has been developed and implemented to complement experimental efforts to improve the quality of ICF target shells produced via controlled-mass microencapsulation. The model provides an efficient means to explore the effect of processing variables on the dynamics of shell dimensions, concentricity, and phase behavior. Comparisons with experiments showed that the model successfully predicts the evolution of wall thinning and core/wall density differences. The model was used to efficiently explore and identify initial wall compositions and processing temperatures which resulted in concentricity improvements from 65 to 99%. The evolution of trace amounts of water entering into the shell wall was also tracked in the simulations. Comparisons with phase envelope estimations from modified UNIFAP calculations suggest that the water content trajectory approaches the two-phase region where vacuole formation via microphase separation may occur.

This note summarizes the results of the single crystal monochromator high-heat-load tests performed at the CHESS F-2 wiggler station. The results from two different cooling geometries are presented: (1) the ``pin-post`` crystal and (2) the ``criss-cross`` crystal. The data presented were taken in August 1993 (water-cooled pin-post) and in April 1995 (water- and gallium-cooled pin-post crystal and gallium-cooled criss-cross crystal). The motivation for trying these cooling (or heat exchanger) geometries is to improve the heat transfer efficiency over that of the conventional slotted crystals. Calculations suggest that the pin-post or the microchannel design can significantly improve the thermal performance of the crystal. The pin-post crystal used here was fabricated by Rocketdyne Albuquerque Operations. From the performance of the conventional slotted crystals, it was thought that increased turbulence in the flow pattern may also enhance the heat transfer. The criss-cross crystal was a simple attempt to achieve the increased flow turbulence. The criss-cross crystal was partly fabricated in-house (cutting, etching and polishing) and bonded by RAO. Finally, a performance comparison among all the different room temperature silicon monochromators that have been tested by the APS is presented. The data includes measurements with the slotted crystal and the core-drilled crystals. Altogether, the …

The Bonneville Power Administration (Bonneville) must ensure that the costs of its contracts for energy resources are as low as reasonably possible and that the resources are needed. During the audit, we reviewed Bonneville`s energy resource programs and focused on its purchase of electrical output from natural gas fired combustion turbines. The objective of this audit was to determine if Bonneville paid excessive costs to acquire the electrical output from combustion turbine facilities. The audit showed that Bonneville contracted to purchase the output from a combustion turbine facility at excessive cost, and that the electricity was not needed. The cost of the electricity under this contract exceeded the amount of revenue Bonneville could obtain by selling it. Bonneville estimated it would operate the generation facility for only 6 months of the year; the contract, however, required Bonneville to pay the fixed costs of the facility during the other 6 months. Consequently, the cost of the electricity plus the fixed costs in the first year of the contract would exceed revenues by $20.9 million. The contract also contained cost escalators that exceeded the rate of inflation. These cost escalators combined with the excessive initial cost resulted in projected excessive costs of …

There is a need to estimate the effect of environmental conditions on construction materials to be used in the repository at Yucca Mountain. Previous reports from this project have demonstrated that it is important to develop an understanding of microbially influenced degradation (MID) development and its influence on massive concrete structures. Further, it has been shown that the most effective way to obtain quantitative data on the effects of MID on the structural integrity of repository concrete is to study manmade, analog structures known to be susceptible to MID. The cooling tower shell located at the Ohaaki Power Station near Wairakei, New Zealand is such a structure.

Concern has been expressed that hydrogen produced by corrosion, radiolysis, and decomposition of the waste could cause embrittlement of the carbon steel waste tanks at Hanford. The concern centers on the supposition that the hydrogen evolved in many of the existing tanks might penetrate the steel wall of the tank and cause embrittlement that might lead to catastrophic failure. This document reviews literature on the effects of hydrogen on the carbon steel proposed for use in the Multi-Function Waste Tank Facility for the time periods before and during construction as well as for the operational life of the tanks. The document draws several conclusions about these effects. Molecular hydrogen is not a concern because it is not capable of entering the steel tank wall. Nascent hydrogen produced by corrosion reactions will not embrittle the steel because the mild steel used in tank construction is not hard enough to be susceptible to hydrogen stress cracking and the corrosion product hydrogen is not produced at a rate sufficient to cause either loss in tensile ductility or blistering. If the steel intended for use in the tanks is produced to current technology, fabricated in accordance with good construction practice, postweld heat treated, and …

A pressure dependent kinetic mechanism for propane oxidation is developed and compared to experimental data from a high pressure flow reactor. The experiment conditions range from 10--15 atm, 650--800 K, and were performed at a residence time of 200 {micro}s for propane-air mixtures at an equivalence ratio of 0.4. The experimental results include data on negative temperature coefficient (NTC) behavior, where the chemistry describing this phenomena is considered critical in understanding automotive engine knock and cool flame oscillations. Results of the numerical model are compared to a spectrum of stable species profiles sampled from the flow reactor. Rate constants and product channels for the reaction of propyl radicals, hydroperoxy-propyl radicals and important isomers with O{sub 2} were estimated using thermodynamic properties, with multifrequency quantum Kassel Theory for k(E) coupled with modified strong collision analysis for fall-off. Results of the chemical kinetic model show an NTC region over nearly the same temperature regime as observed in the experiments. The model simulates properly the production of many of the major and minor species observed in the experiments. Numerical simulations show many of the key reactions involving propylperoxy radicals are in partial equilibrium at 10--15 atm. This indicates that their relative concentrations are …

This document establishes the technical basis in support of Emergency Planning Activites for the 283-E and 283-W Facilities on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated.

This document records the data quality objectives (DQO) process applied to the organic complexant safety issue at the Hanford Site. Two important outputs of this particular DQO application were the following: (1) decision rules for categorizing organic tanks; and (2) analytical requirements that feed into the tank-specific characterization plans. The decision rules developed in this DQO allow the organic tanks to be categorized as safe, conditionally safe, or unsafe based on fuel and moisture concentrations. Then analytical requirements from this DQO process fall into two groups, primary and secondary. The primary data requirements are always applied, while the secondary requirements are only necessary on those half segment samples that violate the fuel and moisture decision rules or that propagate during adiabatic calorimetry testing.

Flammable gases generated in radioactive liquids. Twenty-five high level radioactive liquid waste storage tanks located underground at the Hanford Site are on a Flammable Gas Watch List because they contain waste which tends to retain the gases generated in it until rather large quantities are available for sudden release to the tank head space; if a tank is full it has little dome space, and a flammable concentration of gases could be produced--even if the tank is ventilated. If the waste has no tendency to retain gas generated in it then a continual flammable gas concentration in the tank dome space is established by the gas production rate and the tank ventilation rate (or breathing rate for unventilated tanks); this is also a potential problem for Flammable Gas Watch List tanks, and perhaps other Hanford tanks too. All Flammable Gas Watch List tanks will be fitted with Standard Hydorgen Monitoring Systems so that their behavior can be observed. In some cases, such as tank 241-SY-101, the data gathered from such observations will indicate that tank conditions need to be mitigated so that gas release events are either eliminated or rendered harmless. For example, a mixer pump was installed in tank …

Uranium fuel assemblies and other uranium associated with the shutdown N Reactor are stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility (Facility). The 3712 Building, where the majority of the fuel assemblies and other uranium is stored, is where there could be a potential for a criticality bounding case. The purpose of this study is to evaluate the probability of potential fires in the Facility 3712 Building that could lead to criticality. This study has been done to support the criticality update. For criticality to occur, the wooden fuel assembly containers would have to burn such that the fuel inside would slump into a critical geometry configuration, a sufficient number of containers burn to form an infinite wide configuration, and sufficient water (about a 17 inch depth) be placed onto the slump. To obtain the appropriate geometric configuration, enough fuel assembly containers to form an infinite array on the floor would have to be stacked at least three high. Administrative controls require the stacks to be limited to two high for 1.25 wt% enriched finished fuel. This is not sufficient to allow for a critical mass regardless of the fire and accompanying water moderation. It should …

This is the Savannah River Technology Center Monthly Report for February 1995

Strip logs for 491 wells were produced from a digital subsurface database of lithologic descriptions of the Ferron Sandstone Member of the Mancos Shale. This subsurface database covers wells from the parts of Emery and Sevier Counties in central Utah that occur between Ferron Creek on the north and Last Chance Creek on the south. The lithologic descriptions were imported into a logging software application designed for the display of stratigraphic data. Strip logs were produced at a scale of one inch equals 20 feet. The strip logs were created as part of a study by the Utah Geological Survey to develop a comprehensive, interdisciplinary, and qualitative characterization of a fluvial-deltaic reservoir using the Ferron Sandstone as a surface analogue. The study was funded by the U.S. Department of Energy (DOE) under the Geoscience/Engineering Reservoir Characterization Program.

Transmission electron microscopy (TEM) was used to characterize the microstructures at and near the weld interface in upset welded Type 304L stainless steel test samples. Two sample configurations were examined in this study; upset welded cylinders prepared using a commercial resistance welder and cylindrical shaped samples welded in a Gleeble 1500 thermomechanical simulation device. The Gleeble samples evaluated were welded at 800 C, 900 C and 1,200 C with a 0.5 cm weld upset. The base microstructure of the samples varied with weld temperature. The lower temperature specimens contained a large free-dislocation density and distinct dislocation cells. The higher temperature specimens contained well-developed subgrains and a much lower free-dislocation density. The microstructure of the upset welded samples most closely resembled the 1,200 C Gleeble sample. No distinct bond line was observed by TEM in any of the specimens, i.e., diffusion and grain growth occurred across all weld interfaces. However, weld interfaces in both specimen configurations were characterized by the presence of 50--300 nm diameter particles spaced between 300 and 1,300 nm apart. Through the use of electron diffraction analysis and X-ray microanalysis two precipitate types were identified in both specimen configurations. A crystalline phase very similar to Mn{sub 1.5}Cr{sub 1.5}O{sub …

This report contains data pertaining to the geological and petrophysical characterization of the Ferron Sandstone for 3-D simulation of a Fluvial-Deltaic reservoir.

CONSOL Inc., the University of Kentucky/Center for Applied Energy Research (CAER), and LDP Associates are conducting a three-year research program to explore the technical and economic feasibility of a novel direct coal liquefaction concept. The purpose of this research program is to explore a new approach to direct coal liquefaction in which the primary coal dissolution step is effected by chemical rather than thermal cleavage of bonds in the coal. This is done at a temperature which is significantly lower than that typically used in conventional coal liquefaction. Reaction at this low temperature results in high conversion of the coal to a solubilized form, with little hydrocarbon gas make, and avoids the thermally induced retrograde reactions which are unavoidable in conventional thermal processes. In addition, for low-rank coals, a substantial portion of the oxygen in the coal is removed as CO and CO{sub 2} during the dissolution. The higher selectivity to liquid products and rejection of oxygen as carbon oxides should result in improved hydrogen utilization. The basis of the novel concept is the discovery made by CONSOL R&D that certain hydride transfer agents are very active for coal dissolution at temperatures in the range of 350{degree}C. Because of the …

The authors melted and cast an aluminum-uranium (Al-U) alloy by vacuum induction melting (VIM) prealloyed buttons made by arc melting. The resulting alloy casting displayed a large compositional gradient from top to bottom. The authors sampled the resulting casting for uranium to check homogeneity. The sampling revealed that the top of the casting contained 23.5 wt% uranium, and the bottom (an average of two samples) contained 42.4 wt% uranium. Although each button contained 36.5% uranium, these analyses show that the solidified casting was inhomogeneous. If the buttons were homogeneous, the segregation occurred during induction melting, and this method may not be feasible for making AL-U alloys. If the buttons were not homogeneous, perhaps arc melting the buttons more times would have helped. Bottom pouring the Al-U melt into a mold for faster cooling could also help prevent segregation.

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-SX-103.

Three auger samples from Tank AW-101 were received by the 222-S laboratories. They were analyzed to support the crust burn safety issue. No sample results exceeded the notification criteria.