Sampling Procedure: This project requires a carefully coordinated sample preparation procedure that will ensure that specimens of the proper size and physical characteristics are available for the various measurement methods used. Coherent blocks of coal will be collected in the field, with subsamples being removed in the lab by 1 inch-diameter core drill. At least 5 separate cores will be drilled from each block. Coal blocks sampled in the field will be approximately 10 inches (times) 10 inches {times} 6 inches. Distinctive compositional lithologies should be selected for sampling. For example, a section of the seam containing particularly thick vitrain or durain bands might be selected; or the block might include a mineral matter rich layer. If necessary, several blocks should be selected to represent a range in compositions. Sampling procedure must include a method for retaining moisture. The sample must not be allowed to dry out. Exposure to atmospheric oxygen should be limited as much as possible. The samples must carefully packed for shipment so as to preserve their integrity.

Sampling Procedure: This project requires a carefully coordinated sample preparation procedure that will ensure that specimens of the proper size and physical characteristics are available for the various measurement methods used. Coherent blocks of coal will be collected in the field, with subsamples being removed in the lab by 1 inch-diameter core drill. At least 5 separate cores will be drilled from each block. Coal blocks sampled in the field will be approximately 10 inches (times) 10 inches {times} 6 inches. Distinctive compositional lithologies should be selected for sampling. For example, a section of the seam containing particularly thick vitrain or durain bands might be selected; or the block might include a mineral matter rich layer. If necessary, several blocks should be selected to represent a range in compositions. Sampling procedure must include a method for retaining moisture. The sample must not be allowed to dry out. Exposure to atmospheric oxygen should be limited as much as possible. The samples must carefully packed for shipment so as to preserve their integrity.

Following the First International Conference on Radioactive Nuclear Beams'' in Berkeley, a workshop was held on October 19, 1989 at the Lawrence Berkeley Laboratory to discuss plans for a National High Intensity Radioactive Nuclear Beam (RNB) Facility. The purpose of the workshop was -- after having discussed during the conference the physics question that can be addressed with RNBs -- to evaluate more concretely the possibilities for actually constructing such a facility in this country. It is becoming increasingly apparent that facility producing beams of radioactive nuclei with extreme neutron-to-proton ratios is of high scientific interest and technically feasible. It would allow the study of nuclear structure and astrophysical reactions very far from the line of stable nuclei, and could provide new possibilities of reaching the long-sought island of stability of superheavy nuclei. Such facilities are under advanced consideration in Japan and at CERN in Europe. This paper contains a slightly edited transcript of the tape recording that was made of the workshop.

This paper is the final report for a project to do characterization studies on the KrF laser system. The project did experimental work on KrF lasers in support of modeling studies, with the objective being to see if this technology could be competitive for use in the ICF program. This program has provided LANL with data critical for their model development. Section 2 describes the laser extraction experiments together with the calibration of the diagnostics and the re-examination of the analysis procedure. Section 3 discusses the gain and transient absorption measurements, and Section 4 gives the conclusion for this program.

The goal of this research is to develop catalysts that directly convert methane and light hydrocarbons to intermediates that later can be converted to either liquid fuels or value-added chemicals, as economics dictate. In this reporting period, we have utilized samples of magnesia differing in their pretreatment temperature. Both the hydrido-ruthenium complex H{sub 4}Ru{sub 4}(CO){sub 12} and its reaction product with triethyl aluminum were reacted with these samples. The two ruthenium clusters are expected to react with the magnesia surface in different ways: by deprotonation of the hydride through an acid-base reaction with the basic surface, or by hydrolysis of the aluminum-carbon bond of the triethyl aluminum adduct. The concentration of hydroxyl groups on the magnesia surface able to hydrolyze the aluminum-carbon bond for immobilation should vary depending on the temperature of the pretreatment; the concentration of basic sites which can deprotonate the cluster should also vary with temperature. These differences were borne out by the experiment. We also compared the activity of two batches of AlRu{sub 4}/MgO which had been synthesized at different times in the project. Both batches had approximately the same activity, but the newer batch had greater selectivity for C{sub 6+} hydrocarbons.

The TNX Area post-Cretaceous hydrogeological section consists of an unconfined aquifer in recent to Pliestocene age sediments and a confined aquifer in tertiary aged sediments. The unconfined aquifer is a local water bearing reservoir and will not be correlated to a specific stratigraphic unit at this time. Depth to the water table ranges from 25 feet at the New TNX Seepage Basin to 50 feet at the Old TNX Seepage Basin. The unconfined aquifer is 45--50 feet thick and outcrops in the swamp to the west of TNX. The hydraulic gradient in the unconfined aquifer decreases westerly across the TNX Area from 0.05 to 0.01. The unconfined aquifer is separated from the underlying confined aquifer by a sandy slit aquitard (A1) which is approximately 5--10 feet thick. Researchers reported an increase in hydraulic head across this unit of approximately 8 feet which results in an upward gradient between the unconfined and confined aquifer. The confined Tertiary aquifer (C1) at TNX is 25--30 feet thick and can generally be found 60 to 90 feet below the surface. The C1 aquifer is part of the aquifer commonly referred to as the Congaree'' which occurs in the Congaree Formation. The C1 aquifer lies …

When one attempts to construct classical wormholes in Minkowski signature Lorentzian spacetimes violations of both the weak energy hypothesis and averaged weak energy hypothesis are encountered. Since the weak energy hypothesis is experimentally known to be violated quantum mechanically, this suggests that a quantum mechanical analysis of Minkowski signature wormholes is in order. In this note I perform a minisuperspace analysis of a simple class of Minkowski signature wormholes. By solving the Wheeler-de Witt equation for pure Einstein gravity on this minisuperspace the quantum mechanical wave function of the wormhole is obtained in closed form. The wormhole is shown to be quantum mechanically stabilized with an average radius of order the Planck length. 8 refs.

316L stainless steel is a candidate material for construction of equipment that will be exposed to tritium. Proper design of the equipment will require an understanding of how tritium and its decay product helium affect mechanical properties. This memorandum describes results of rapid heating tensile testing of hydrogen-charged specimens of high-energy-rate-forged (HERF) 316L stainless steel. These results provide a data base for comparison with uncharged and tritium-charged-and-aged specimens to distinguish the effects of hydrogen and helium. Details of the experimental equipment and procedures and results for uncharged specimens were reported previously. 3 refs., 10 figs.

During the current reporting period a total of 139 samples (46 DOE Sample Bank samples and 93 other Penn State samples) of various sizes were distributed. Sixty-three of the samples were distributed to DOE or its contractors; 76 were distributed to other agencies. A total of 88 data printouts were distributed. In addition, seven special data requests were fulfilled by either search/sort and printout or creation of a data disk. Several preliminary requests for Sample Bank and Data Base information have also been handled.

During the current reporting period a total of 139 samples (46 DOE Sample Bank samples and 93 other Penn State samples) of various sizes were distributed. Sixty-three of the samples were distributed to DOE or its contractors; 76 were distributed to other agencies. A total of 88 data printouts were distributed. In addition, seven special data requests were fulfilled by either search/sort and printout or creation of a data disk. Several preliminary requests for Sample Bank and Data Base information have also been handled.

The international workshop brought together 170 participants to further develop the SSC design and performance specifications of the LAr, Gas, Scintillation, Silicon, and Warm Liquid calorimeter technologies, and to develop the general topics of Requirements, Simulation, and Electronics. Progress was made across a broad front in all areas; at the feasibility level for some and In the fine structure for others. The meeting established areas of agreement, provided some general direction, and helped to quantify some differences at widely varying levels of detector technology development. The workshop helped to level the different understandings of the participants; increased the depth of the generalists and the breadth of the specialists. A high degree of group partitioning limited access to the detailed discussion within some detector groups. The communication was clearly necessary and rewarding, and seemed to meet or exceed the expectations of most participants. This report will deal with: the Liquid Argon detector and, to a lesser extent, the Requirements working groups, an update on uranIum material logistics, and a view of LAr calorimetry by others.

The liquid argon dewar and the three cryostats which contain the modules of the D-Zero detector are cooled and maintained at a low pressure equilibrium by the use of liquid nitrogen cooling loops. The dewar has one vacuum jacketed valve at the inlet of the cooling loop and one at the outlet. Each cryostat has two inlet valves, one for the cooldown loops and one for the operating loops. in addition to an outlet valve. The flow rate of the liquid nitrogen, and hence the valve sizes and corresponding flow coefficients (C{sub v}), is deter mined by the required cooling rate of each system. The large variance between the cooling rate required for cooldown and that required for operation, and the high control resolution required, makes the selection of a valve seat and plug difficult. The liquid valve coefficient calculations do not specifically consider the size affect of gas generated within the valve by adiabatic pressure drop. See Appendix I for a calculation of the magnitude of this effect. The figures and a graphical and tabular summary of the papers conclusions are presented in Appendix II.

New measurements of the neutron and gamma-ray emission spectra from materials of interest to thermonuclear reactors with a 14 MeV neutron source were done during 1986 and 1987. These measurements characterized by better resolution than those reported in the Summary published in 1982, were performed using the pulsed sphere and time-of-flight techniques. The detector used in these measurements was a NE-213 cylinder, 5.08 cm in diameter by 5.08 cm thick. The new measurements include the following materials: Be, C, N, H/sub 2/O, C/sub 2/F/sub 4/ (teflon), Al, Si, Ti, Fe, Cu, Ta, W, Au, Pb, /sup 232/Th, and /sup 238/U. For all these materials, both the neutron and gamma emission spectra were measured. A complete tabulation of all the measurements done under the Pulse Sphere Program is presented. 37 refs., 1 tab.

We present a novel approach to the 3-dimensional high-gain free- electron laser amplifier problem. The method allows us to write the laser field as an integral equation which can be efficiently and accurately evaluated on a small computer. The model is general enough to allow the inclusion of various initial electron beam distributions to study the gain reduction mechanism and its dependence on the physical parameters. 16 refs., 8 figs., 1 tab.

In this report, I present results of a theoretical 1-D model discussed by G. Dattoli, A. Reniere and myself. The validity of a steady-state analysis is discussed and some estimates are given of the effects introduced by the ''lethargy'' of the laser pulse due to the finite length of the e/sup /minus// pulse. Also, I present analytical expressions for the laser pulse in terms of supermodes (wave-packets of cavity modes), their evolution, physical width as well as the associated frequency spectrum. Next, I present results obtained with a 3-D code for the single pass, small-signal gain. In the appendix, I summarize the symbols used in this report. 2 refs., 6 figs., 3 tabs.

The observation of an anti-Stokes satellite in the spectrum of light backscattered from a CO{sub 2} laser plasma is reported. Its origin is found to be Thomson scattering of the incident light from a counterpropagating mode-coupled plasma wave. The parent electron and ion waves in the mode-coupling process were driven by stimulated Raman and Brillouin backscattering. The parent and daughter plasma waves were detected by ruby laser Thomson scattering. A computer simulation modeling the experiment shows further cascading of the Stokes backscattered light to lower frequencies, apparently due to its rescattering by another, higher phase velocity, counterpropagating coupled mode. Comparisons with theoretical predictions are presented. 16 refs., 4 figs.

The radiological safety hazards of the experimental area (EA) for the proposed Inertial Confinement Fusion (ICF) Laboratory Microfusion Facility (LMF) have been examined. The EA includes those structures required to establish the proper pre-shot environment, point the beams, contain the pellet yield, and measure many different facets of the experiments. The radiation dose rates from neutron activation of representative target chamber materials, the laser beam tubes and the argon gas they contain, the air surrounding the chamber, and the concrete walls of the experimental area are given. Combining these results with the allowable dose rates for workers, we show how radiological considerations affect access to the inside of the target chamber and to the diagnostic platform area located outside the chamber. Waste disposal and tritium containment issues are summarized. Other neutronics issues, such as radiation damage to the final optics and neutron heating of materials placed close to the target, are also addressed. 16 refs., 2 figs., 1 tab.

This report quantifies certain characteristics of the rotary bayonets and associated platform piping on the DO detector. The Vacuum Jacketed 4-inch x 6-inch and 1.5-inch x 3-inch and the 4-inch and 6-inch vacuum pipe articulating jumpers are considered here. The values of greatest importance are the forces required at the bayonet moment arms given in Table II and the stresses summarized in Table III. The forces required should be noted and checked that they are acceptable to the problem. The maximum bending stresses of the vacuum pipes do not exceed 1000 psi and are essentially negligible. The 4-inch x 6-inch vacuum jacketed line experiences the maximum bending stress of 10,300 psi. According to code B31.1, the maximum allowable bending stress is 25,500 psi. The major sources of error in these calculations should be summarized. First, all weights used were approximations and all lengths used were scaled from drawings. Second, while the FRAME MAC{trademark} models resemble the vacuum pipe articulating jumpers, they are definitely simplified. For instance, they do not account for the different stiffnesses of the unions. Finally, the bayonets in the ANSYS models consist of an outer jacket and an inner pipe fixed together at the end of the …

AMAX Research Development Center (AMAX R D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.

AMAX Research & Development Center (AMAX R&D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.

A heat exchanger is necessary to warm the gaseous nitrogen from the nitrogen dewar from 77 K to ambient temperature for use in the D-Zero Building. The original proposal would use an ambient air vaporizer, but further investigation led to the consideration and evaluation of other possibilities and a different final system. The vaporizer must be able to handle a flow rate of 1200 scfh at 30 psig on a continuous basis subject to local weather conditions. Upon consulting with a representative from Thermax Incorporated, So. Dartmouth, Massachusetts, four different heat exchanging systems were proposed. Their advantages and disadvantages are stated.

This report presents a radiological risk analysis of three representative space mission scenarios utilizing a fission reactor. The mission profiles considered are: a high-altitude mission, launched by a TITAN IV launch vehicle, boosted by chemical upper stages into its operational orbit, a interplanetary nuclear electric propulsion (NEP) mission, started directly from a shuttle parking orbit, a low-altitude mission, launched by the Shuttle and boosted by a chemical stage to its operational orbit, with subsequent disposal boost after operation. 21 refs., 12 figs., 7 tabs.

This paper analyzes the effect of transverse loading on a cable-in-conduit conductor which has been proposed for the toroidal field coils of the International Thermonuclear Experimental Reactor. The primary components of this conductor are a loose cable of superconducting wires, a thin-wall tube for helium containment, and a U-shaped structural channel. A method is given where the geometry of this conductor can be optimized for a given set of operating conditions. It is shown, using finite-element modeling, that the structural channel is effective in supporting loads due to transverse forces and internal pressure. In addition, it is shown that the superconducting cable is effectively shielded from external transverse loads that might otherwise degrade its current carrying capacity. 10 refs., 10 figs., 3 tabs.

Two core holes have been completed on the flanks of Newberry Volcano, Oregon. Core hole GEO N-1 has a heat flow of 180 mWm-2 reflecting subsurface temperature sufficient for commerical exploitation of geothermally generated electricity. GEO N-3, which has a heat flow of 86 mWm-2, is less encouraging. Considerable emphasis has been placed on the ''rain curtain'' effect with the hope that a detailed discussion of this phenomenon at two distinct localities will lead to a better understanding of the physical processes in operation. Core hole GEO N-1 was cored to a depth of 1387 m at a site located 9.3 km south of the center of the volcano. Core hole GEO N-3 was cored to a depth of 1220 m at a site located 12.6 km north of the center of the volcano. Both core holes penetrated interbedded pyroclastic lava flows and lithic tuffs ranging in composition from basalt to rhyolite with basaltic andesite being the most common rock type. Potassium-argon age dates range up to 2 Ma. Difficult drilling conditions were encountered in both core holes at depths near the regional water table. Additionally, both core holes penetrate three distinct thermal regimes (isothermal (the rain curtain), transition, and …