Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure and alloy content, viz., martensitics, bainitics, delta ferritics, and duplex steels. The low alloy bainitic steels (Fe-2-1/4Cr-1Mo) undergo extensive decarburization when exposed to high temperature flowing sodium. It is for this reason that ferritic steels with higher chromium (9 to 12% Cr) content have been proposed to minimize the carbon transfer and eventual degradation of mechanical properties. The martensitic steels, HT-9 and improved Fe9Cr1Mo are being considered as cladding/duct materials for liquid metal reactors (LMR). The alloy HT-9 is based on 12Cr1Mo composition. The improved Fe9Cr1Mo alloy is based on 9Cr1Mo composition as its name implies. The objective of the work reported here is to evaluate the sodium compatibility of the alloys at temperatures and flow rates typical of LMR cores. Testing was done for 8104 hours at 60/sup 0/C and 3992 hours …

The linearized drift kinetic equation is solved numerically to obtain the Onsager transport matrix for a three-dimensional toroidal plasma confinement geometry. Local transport coefficients relating the cross-field fluxes to the thermodynamic forces are computed as continuous functions of the collision frequency. In particular, in the low-collision-frequency regime (..nu.. < ..omega../sub b/), the transport resulting from the nonconservation of the longitudinal adiabatic invariant J (due to particle transitions from helically trapped to toroidally trapped) is obtained. The boundary layer in velocity space resulting from these transition particles can be accurately treated using a Legendre polynomial representation for the pitch angle dependence of the distribution function. Magnetic coordinates are used so that finite-beta effects are included. The disparity in the time scales between collisionless particle orbits and collisional dynamics is treated efficiently to obtain steady-state fluxes and viscosity coefficients. This yields significant improvements in the precision and computational effort in comparison with Monte Carlo methods. The effect of a radial electric field in the ..nu.. < ..omega../sub D/ regime is studied. Applications to Advanced Transition Facility (ATF) and heliac configurations are given.

Using a transport code combined with an ion Bernstein wave tokamak ray tracing code, a modelling code for the ion Bernstein wave heating has been developed. Using this code, the ion Bernstein wave heating experiment on the JIPPT-II-U tokamak has been analyzed. It is assumed that the resonance layer is formed by the third harmonic of deuterium-like ions, such as fully ionized carbon, and oxygen ions near the plasma center. For wave absorption mechanisms, electron Landau damping, ion cyclotron harmonic damping, and collisional damping are considered. The characteristics of the ion Bernstein wave heating experiment, such as the ion temperature increase, the strong dependence of the quality factor on the magnetic field strength, and the dependence of the ion temperature increment on the input power, are well reproduced.

Evaluation of the thermohydrological conditions near high-level waste packages is needed for the design of the waste canister and for overall repository design and performance assessment. Most available studies in this area have assumed that the hydrologic properties of the host rock do not change in response to the thermal, mechanical or chemical effects caused by waste emplacement. However, the ramifications of this simplifying assumption have not been substantiated. We have studied dissolution and precipitation of silica in thermally driven flow systems, including changes in formation porosity and permeability. Using numerical simulation, we compare predictions of thermohydrological conditions with and without inclusion of silica redistribution effects. Two cases were studied, namely, a canister-scale problem, a repository-wide thermal convection problem, and different pore models were employed for the permeable medium (fractures with uniform or non-uniform cross sections). We find that silica redistribution generally has insignificant effects on host rock and canister temperatures, pore pressures, or flow velocites.

This Current Year Work Plan presents in detail a description of the activities to be performed by the Joint Integration Office/RI during FY86. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO/RI by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO/RI tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance development, task monitoring, task progress information gathering and reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of reports for DOE detailing program status. Program Analysis is performed by the JIO/RI to support identification and assessment of alternatives, and development of long-term TRU waste program capabilities. These analyses include short term analyses in response to DOE information requests, along with performing an RH Cost/Schedule Optimization report. System models will be developed, updated, and upgraded as needed to enhance JIO/RI's capability to evaluate the adequacy of program efforts in various fields. A TRU …

The Defense TRU Waste Program (DTWP) is the focal point for the Department of Energy is national planning, integration, and technical development for TRU waste management. The scope of this program extends from the point of TRU waste generation through delivery to a permanent repository. The TRU program maintains a close interface with repository development to ensure program compatibility and coordination. The defense TRU program does not directly address commercial activities that generate TRU waste. Instead, it is concerned with providing alternatives to manage existing and future defense TRU wastes. The FY 86 Program Plan is consistent with the Defense TRU Waste Program goals and objectives stated in the Defense Transuranic Waste Program Strategy Document, January 1984. The roles of participants, the responsibilities and authorities for Research Development (R D), the organizational interfaces and communication channels for R D and the establishment of procedures for planning, reporting, and budgeting of all R D activities meet requirements tated in the Technical Management Plan for the Transuranic Waste Management Program. The Program Plan is revised as needed. Detailed budget planning (i.e., programmatic funding and capital equipment) is presented for FY 86; outyear budget projections are presented for future years.

On November 16, 1984 a leak was discovered in one of the Fast Flux Test Facility (FFTF) Primary Sodium Sampling System electromagnetic pumps. The leak was discovered in the course of routine cell entry to investigate a shorted trace heat element. The purpose of this paper is to describe the circumstances surrounding the occurrence of the leak, the actions taken to replace the damaged pump and the additional steps which were necessary to return the plant to power. In addition, the processes involved in producing the leak are described briefly. The relative ease of recovery from this incident is indicative of the overall feasibility of the Liquid Metal Reactor (LMR) operational concept.

The Ion Beam Facility operated for 6000 machine hours last year, ranging in energy from 300 Kev to 24 Mev. Improvements include cryopumps replacing diffusion pumps, a rebuilding of the tandem chopper electronics and the vertical's corona charging system. Methane molecules were successfully accelerated by the vertical in quantities of hundreds of nanoamperes. Two replacement magnet power supplies on the tandem and a completely new capacitor shell regulator on the vertical are soon to be installed.

This report describes a method for determining yttrium in plutonium using an anion-exchange separation and x-ray fluorescence. We add zirconium to the plutonium solution as an internal standard. We oxidize the plutonium to Pu + 4 and pass the solution through an anion-exchange column with 8M HCl. The Pu + 4 sorbs to the resin and the yttrium and zirconium pass through completely. We evaporate the eluate solution containing the yttrium and zirconium and transfer it to a 10-ml volumetric flask. We add a portion of this solution to an x-ray cell and measure the Ka x-ray line for both yttrium and zirconium. The ratio of yttrium to zirconium is then compared with standards. This method has a precision of 0.84% relative standard deviation for yttrium over a concentration range of 0.5 to 3.5 mg in a 10-ml volume. 1 ref., 2 figs., 2 tabs.

This thesis describes the measurement of Stark amplitude coefficients and US for the 6SP/sub 1/2/ 7SP/sub 1/2/ transition of SVTl in an external static electric field E. The coefficient is determined by measuring the absorption of linearly polarized 293 nm light at the F=1 F'=1 resonance in a cell with known electric field and interaction length, and calibrated thallium density. Then US is determined from the ratio US S/ S of intensities of the F=0 F=1 and F=0 F=0 resonance lines in fluorescence. The final results are = (1.30 +- 0.06) x 10 V 0 cm/V and US = (1.08 +- 0.05) x 10 V 0 cm/V (where 0 = electron Bohr magneton). US is combined with a previous measurement of Im EPSILON/sub p//US to yield the parity non-conserving electric dipole amplitude EPSILON/sub p/. 25 refs., 25 figs., 1 tab.

The Ion Cyclotron Resonant Heating (ICRH) slot antenna has been a part of the ion and electron plasma heating system in the central cell region of the Tandem Mirror Experiment-Upgrade (TMX-U). This paper presents the mechanical design and arrangement of the antenna, coax feed lines, feedthroughs, and matching network for the slot antenna.

The Hot Dry Rock Geothermal Energy Development Program has focused worldwide attention on the facts that natural heat in the upper part of the earth's crust is an essentially inexhaustible energy resource which is accessible almost everywhere, and that practical means now exist to extract useful heat from the hot rock and bring it to the earth's surface for beneficial use. The Hot Dry Rock Program has successfully constructed and operated a prototype hot, dry rock energy system that produced heat at the temperatures and rates required for large-scale space heating and many other direct uses of heat. The Program is now in the final stages of constructing a larger, hotter system potentially capable of satisfying the energy requirements of a small, commercial, electrical-generating power plant. To create and understand the behavior of such system, it has been necessary to develop or support the development of a wide variety of equipment, instruments, techniques, and analyses. Much of this innovative technology has already been transferred to the private sector and to other research and development programs, and more is continuously being made available as its usefulness is demonstrated. This report describes some of these developments and indicates where this new technology …

Magnetic drift pumping on TMX-U involves driving four antennae through high Q-resonant circuits. One of the key elements in the resonant circuit is a variable inductor able to carry the 3500 amperes through the circuit and maintain its shape and inductance. The eight resonant circuits can be combined to feed the four antennae with one or two frequencies on each antenna, or frequency shift keying between two frequencies. Each resonant circuit is fed by two 10 to 30 kHz exciters capable of delivering 80 kW each to the circuit. Each exciter receives its power from its own adjustable 0 to 400 volt power supply. The entire system is controlled by a CAMAC control system over a fiber-optic link. The control system checks interlock status, controls ''On'' and ''Off'' status, calculates and adjusts phasing of the exciters for addition or deletion of the proper beat frequencies, and monitors operation. 3 refs., 5 figs.

The nuclear spin interactions and the associated quantum mechanical dynamics which are present in solid state NMR are introduced. A brief overview of aluminosilicate structure is presented and crystalline structure is then reviewed, with emphasis on the contributions made by /sup 29/Si NMR spectroscopy. The local structure of glass aluminosilicates as observed by NMR, is presented with analysis of the information content of /sup 29/Si spectra. A high-temperature (to 1300/sup 0/C) NMR spectroscopic investigation of the local environment and dynamics of molecular motion in molten aluminosilicates is described. A comparison is made of silicate liquid, glass, and crystalline local structure. The atomic and molecular motions present in a melt are investigated through relaxation time (T/sub 1/ and T/sub 2/) measurements as a function of composition and temperature for /sup 23/Na and /sup 29/Si.

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing; results and conclusions described may change as the work continues. 10 figs.

The General Purpose Powder Diffractometer (GPPD), a high resolution ( d/d = 0.002) time-of-flight instrument, exhibits a resolution function that is almost independent of d-spacing. Some of the special properties of time-of-flight scattering data obtained at a pulsed neutron source will be discussed. A method is described that transforms wavelength dependent data, obtained at a pulsed neutron source, so that standard structural least-squares analyses can be applied. Several criteria are given to show when these techniques are useful in time-of-flight data analysis. 14 refs., 6 figs., 1 tab.

The halow recycler is a mechanical device on the Tandem Mirror Experiment Upgrade (TMX-U) that is designed to increase the density at the plasma edge providing enhanced shielding of the core plasma from background neutrals. Each recycler body, which consists of coaxial annular cylinders and a adjacent plenum closely follows the magnetic flux tubes in the transition region of TMX-U. Each plenum is provided with gas feed and pressure measurement systems as well as Langmuir probes. This paper describes the design, fabrication, installation, and operation of these devices.

Present ion sources produce deuterium ions plus small amounts of impurity ions including oxygen. The oxygen current is readily trapped by the Mirror Fusion Test Facility-B (MFTF-B) plasma and represents a severe energy loss mechanism. A pure-beam source-neutralizer has been designed by LLNL for the MFTF-B. This concept uses momentum separation by closely coupling an electromagnet to the source to purify the beam. This design requires a low pressure in the neutralizer, implying a long length and a large diameter for high conductance. Present designs require a 55-in. diameter by 60-in. long magnetically shielded region. This shield encloses the source and the separator magnet, and acts as the neutralizer duct for the beam. The fringe fields from the MFTF-B magnets penetrate the pure-beam neutralizer along the beamline axis. Field strengths on the order of three hundred gauss must be reduced to less than 6 gauss axial and 0.2 gauss transverse to the beam. Conventional single and double layer shielding designs require excessive amounts of permeable material. Multiple layer shields using a soft iron outer shield with a highly permeable inner shield require a 4 3/4-in.-thick outer shield. We have rejected this as a possible shielding solution. Active shielding, using two …

The basic physical problem of NMR spatial localization is considered. To study diseased sites, one must solve the problem of adequately localizing the NMR signal. We formulate this as an inverse problem. As the NMR Bloch equations determine the motion of nuclear spins in applied magnetic fields, a theoretical study is undertaken to answer the question of how to design magnetic field configurations to achieve these localized excited spin populations. Because of physical constraints in the production of the relevant radiofrequency fields, the problem factors into a temporal one and a spatial one. We formulate the temporal problem as a nonlinear transformation, called the Bloch Transform, from the rf input to the magnetization response. In trying to invert this transformation, both linear (for the Fourier Transform) and nonlinear (for the Bloch Transform) modes of radiofrequency excitation are constructed. The spatial problem is essentially a statics problem for the Maxwell equations of electromagnetism, as the wavelengths of the radiation considered are on the order of ten meters, and so propagation effects are negligible. In the general case, analytic solutions are unavailable, and so the methods of computer simulation are used to map the rf field spatial profiles. Numerical experiments are also …

We have installed a new diagnostic instrument to investigate ions emanating along magnetic-field lines of the TMX-U tandem-mirror experiment. This analyzer contains parallel electric and magnetic fields, which yield ion mass and energy spatial separation. A dual array of 128 copper collector plates detects particles in the ion flux that is first collimated and then focused through the 180-degree bending magnetic field. An electric field applied transverse to the bending particle path then separates the ion masses in the direction perpendicular to the magnetic-pole faces while the magnetic field spreads out the different energies of each mass in a plane parallel to the magnetic-pole tips. The CAMAC-based data recorders are fiber-optically coupled to the system controller for data acquisition, analysis, and display. A commercial CAMAC data recorder was modified for current input. We expect to measure higher particle energies than the present gridded end-loss analyzers as well as to more accurately determine the energy spectra.

The Common Long Pulse Source (CLPS) is designed to meet the differing long pulse neutral beam requirements of TFTR, Doublet III-D, and MFTF-B. The mechanical baseline design to meet these requirements is described along with supporting engineering data collected during the testing of the prototype LBL 10 x 40 Long Pulse Accelerator (LPA) and the Long Pulse Plasma Source (LPS). The CLPS is a scaled up design of the LPA and LPS and can be configured for 120 keV, 70 A D/sub 2/ non-focused, and, 80 keV, 80 A H/sub 2/ or 50 A D/sub 2/ with a 10 m focal length. The two configurations use identical major components, such as accelerator grids, supporting structures, insulators and plasma sources. Ion beam optics are analytically modeled and the results are presented along with the electric field gradients and thermal calculations for various components. A low technology plasma source back plate electron dump design has been adopted. A full scale model of CLPS was constructed, and the baseline design has been transferred to industry. 7 refs., 5 figs.

The purpose of this study is to identify opportunities for photovoltaic (PV) research projects to capitalize on related but non-PV research. The study is performed under the assumption that a considerable body of ongoing semiconductor research in non-PV areas could be of value to its PV Program and the PV community in general. Research related to III-V compounds, thin films, and crystalline silicon materials is included. Research that is known to be PV-related or sponsored by DOE was excluded from consideration. The study resulted in 11 recommendations (research areas) and a subset of 58 specific research projects. In addition, over 75 non-PV research managers in the semiconductor field are identified as potential sources of ideas which could benefit photovoltaics.

The author critiques the model of tokamak edge turbulence by P.W. Terry and P.H. Diamond (Phys. Fluids 28, 1419, 1985). The critique includes a discussion of the physical basis, consistency and quantitative accuracy of the Terry-Diamond model. 19 refs. (WRF)

Properties of the radiation emitted by a plane sinusoidal undulator are calculated in the far field approximation. Software has been developed to calculate the spectral distribution and polarization of the radiated intensity I(E) at a point on (or integrated over) a cross sectional observation plane of the photon beam. Spatial distribution of monochromatic radiation and power density contours are also calculated. Spectral broadening caused by an electron beam of finite spatial distribution is considered. Dispersive properties of the photon beam, including the dependence on deflection parameter, are analyzed. It is shown that reasonably constant intensity distribution I(E) can be obtained by properly shaping the beam acceptance aperture. 5 refs., 11 figs.