An electronics package for a small, battery-operated, self-contained, neutron coincidence counter based on a portable shift-register (PSR) has been developed. The counter was developed for applications not adequately addressed by commercial packages, including in-plant measurements to demonstrate compliance with regulations (domestic and international), in-plant process control, and in-field measurements (environmental monitoring or safeguards). Our package's features, which address these applications, include the following: Small size for portability and ease of installation;battery or mains operation; a built-in battery to power the unit and a typical detector such as a small sample counter, for over 6 h if power lines are bad or noisy, if there is a temporary absence of power, or if portability is desired; complete support, including bias, for standard neutron detectors; a powerful communications package to easily facilitate robust external control over a serial port; and a C-library to simplify creating external control programs in computers or other controllers. Whereas the PSR specifically addresses the applications mentioned above, it also performs all the measurements made by previous electronics packages for neutron coincidence counters developed at Los Alamos and commercialized. The PSR electronics package, exclusive of carrying handle, is 8 by 10 by 20 cm; it contains the circuit …

Los Alamos National Laboratory maintains one of the most complete NDT facilities worldwide. In addition to many fixed pieces of equipment, the Laboratory has a very wide range of NDT and dynamic test diagnostic equipment that can be taken to the job site. Most of the equipment described here was procured for a specific purpose to support a program consistent with the nuclear weapons mission of Los Alamos. However, through the years, the equipment has found use in many other applications both within and external to weapons research, development, and testing. Various combinations of these equipments form unique capabilities, as demonstrated by the applications. The portable equipment is mainly applied to problems where the process or object under study cannot be brought into an NDT laboratory.

The objectives of this project are to determine the long-term chemical reactivity and mechanical durability of a fluidized version of Phillips Petroleum Company`s proprietary Z-SORB sorbent for the desulfurization of coal-derived gases in a high-pressure (20 atm) fluidized-bed reactor under simulated U-Gas conditions and at a moderate operating temperature of 538 degrees C.

J-integral fracture mechanics techniques and electron microscopy observations were used to investigate the effects of tritium and its radioactive decay product, {sup 3}He, on Types 316L, 304L and 21Cr-6Ni-9Mn stainless steels. Tritium-exposed-and-aged steels had lower fracture-toughness values and shallower sloped crack-growth-resistance curves than unexposed steels. Both fracture-toughness parameters decreased with increasing concentrations of {sup 3}He. The fracture-toughness reductions were accompanied by a change in fracture mode from microvoid-nucleation-and-growth processes in control samples to grain-and-twin-boundary fracture in tritium-charged-and-aged samples. Type 316L stainless steel had the highest fracture-toughness values and Type 21Cr-6Ni-9Mn had the lowest. Samples containing {sup 3}He but degassed of tritium had fracture toughness properties that were similar to uncharged samples. The results indicate that helium bubbles enhance the embrittlement effects of hydrogen by affecting the deformation properties and by increasing localized hydrogen concentrations through trapping effects.

Temperatures, densities and confinement of deuterium plasmas confined in tokamaks have been achieved within the last decade that are approaching those required for a D-T reactor. As a result, the unique phenomena present in a D-T reactor plasma can now be studied in the laboratory. Recent experiments on the Tokamak Fusion Test Reactor (TFTR) have been the first magnetic fusion experiments to study plasmas with reactor fuel concentrations of tritium. The injection of {approximately}20 MW of tritium and 14 MW of ceuterium neutral beams into the TFTR produced a plasma with a T/D density ratio of {approximately}1 and yielded a maximum fusion power of {approximately}9.2 MW. The fusion power density in the core of the plasma was {approximately}1.8 MW m{sup {minus}3} approximating that expected in a D-T fusion reactor. A TFTR plasma with T/D density ratio of {approximately}1 was found to have {approximately}20% higher energy confinement time than a comparable D plasma, indicating a confinement scaling with average ion mass, A, of {tau}{sub E} {approximately} A{sup 0.6}. The core ion temperature increased from 30 keV to 37 keV due to a 35% improvement of ion thermal conductivity. Using the electron thermal conductivity from a comparable deuterium plasma, about 50% of …

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Advanced coal-based power systems, such as integrated gasification and pressurized fluidized-bed combustion, require particulate removal at high temperatures and high pressure under adverse chemical conditions. To facilitate the development of advanced coal-based power systems, then Morgantown Energy Technology Center (METC) has assembled a Particulate Cleanup Program, which conducts technology demonstration projects and applied research to address the adverse filtration conditions and filter system issues, as well as the future performance demands of these systems.

We present results for semi-leptonic form-factors obtained on statistical sample of 63 32{sup 3} {times} 64 lattices at {beta} = 6.0 using quenched Wilson fermions. We find f{sub +}{sup D{yields}Klv} (q{sup 2} = 0) = 0.73 {plus_minus} 0.06, A{sub 2}/A{sub 1}(D {yields} K*lv) = 0.79 {plus_minus} 0.23, V/A{sub 1}(D{sub s} {yields} {phi}lv) = 1.89 {plus_minus} 0.04, and A{sub 2}/A{sub 1}(D{sub s} {yields} {phi}lv) = 0.70 {plus_minus} 0.09, where the error estimate includes statistical errors and errors due to extrapolation to q{sup 2} = 0 and to physical values of (m{sub u} + m{sub d})/2 and m{sub s}. The remaining sources of systematic errors are those due to O(a) discretization errors and those due to quenching, which our results indicate may be small. We also comment on the validity of pole-dominance in these form-factors.

The U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), in cooperation with nuclear power plant utilities and the Nuclear Energy Institute, have prepared equipment aging evaluations of nuclear power plant equipment for life extension considerations. Specifically, these evaluations focused on equipment considered important for plant license renewal (U.S. Code of Federal Regulations 10CFR54). {open_quotes}Industry Reports{close_quotes} (IRs), jointly funded by DOE and EPRI, evaluated the aging of major systems, structures, and components (e.g., reactor pressure vessels, Class I structures, PWR and BWR containments, etc.) and contain a mixture of technical and licensing information. {open_quotes}Aging Management Guidelines{close_quotes} (AMGs), funded by DOE, evaluate aging for commodity types of equipment (e.g., pumps, electrical switchgear, heat exchangers, etc.) and concentrate on technical issues only. AMGs are intended for systems engineers and plant maintenance staff. A significant number of technical issues were resolved during IR interactions with the U.S. Nuclear Regulatory Commission (NRC). However, certain technical issues have not been resolved and are considered {open_quotes}open{close_quotes}. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical …

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A picture is worth a thousand words, which explains why digital orthophotographs have become such a popular item. Today, most procurement of orthophotographs result in a digital product. However, if one already has hard copy orthophotography, should one scan them, or have them produced as true digital orthophotographs? What are the advantages and disadvantages of each methodology? This paper examines the procedure the Facility for Information Management, Analysis, and Display (FIMAD) at Los Alamos National Laboratory (LANL) uses to determine the appropriate product based on our needs. The scanned product is compared to a digitally produced orthophotograph, procured through a vendor. Comparison is performed on the screen, on hard copy output, and by spectral analysis in the red, green and blue bands. Full screen sized images look fairly good, but when enlarged, the scanned image appeared blocky and fuzzy. Hard copy output from the electrostatic plotter produces colors similar to the screen for the demo image, but renders poor color matching with the scanned image. Histograms of each band of the scanned image show a high count at the low end of the curve. These findings confirm that the images are different, and that the differences are not just in …

Poly(acrylonitrile) fibers have been pyrolyzed under various conditions to form flexible carbon yarns capable of intercalating lithium ions. These fibers have also been formed into both woven and non woven cloths. Potentiostatic, potentiodynamic and galvanostatic tests have been conducted with these materials in several electrolytes. In some tests, a potential hold was used after each constant current charge and discharge. These tests have shown some of these flexible materials to reversibly intercalate lithium ions to levels that are suitable for use as a practical battery anode.

A method to obtain and process `mountain range` displays of beam signals is described. A custom-made trigger generator and a digital oscilloscope are used for the data acquisition and the graphical interface package LabVIEW is used to process the data. High resolution displays of wall monitor signals updating every AGS cycle have proven very powerful as a beam diagnostic.

The ternary phase diagram of Hf-V-Nb system has been established and the C15 and C14 Laves phase regions located. The structural stability of the cubic Laves phase HfV{sub 2}+Nb was examined using heat capacity measurements and transmission electron microscopy. It is found that the binary C 15 has a martensitic transformation at 115K and that Nb addition can eliminate the martensitic transformation and stabilize the C15 structure. The elastic properties vs. temperature of the C15 HfV{sub 2}+Nb were studied using the resonant ultrasound technique. It is observed that the shear and Young`s moduli increase abnormally with increasing temperature, the bulk modulus is virtually constant, and the Poisson`s ratio is very high and decreases abnormally with increasing temperature. The elastic properties of the C15 compound can be qualitatively understood using the electronic structure obtained from ab initio calculations. The relation between the phase stability and anomalous elastic properties is discussed based on these results.

A program has been initiated to increase the proton fractions extracted from ECR sources by modifying the atom concentration in the source using minor additives to the plasma. A progress report is given.

The COntinuous Reflectometry for Radius vs. Time EXperiment (CORRTEX) system was developed by the Los Alamos National Laboratory for determining the energy released in a nuclear explosion by measuring the position of its shock front as a function of time. The CORRTEX system, fielding techniques, and the methods and software for data reduction and analysis were developed over a 15 year period with hundreds of measurements made on nuclear tests and high explosive experiments. CORRTEX is a compact, portable, fast-sampling, microprocessor-controlled system, based on time domain reflectometry, requiring only a 24 volt power source and a sensing element. Only the sensing element (a length of 50 ohm coaxial cable) is expended during the detonation. In 1979, the CORRTEX system was shown to be ideally suited for chemical explosive performance measurements. Its utility for diagnosing chemical explosives was further demonstrated with successful measurements on large multiple-hole chemical shots in rock quarries and strip mines. Accurate timing of the detonation of sequenced or ripple fired arrays, as well as data characterizing the initiation, explosive performance and detonation anomalies are obtained. This information can serve as the basis for empirical or modeled improvements to blasting operations. A summary of the special CORRTEX features …

As part of the RERTR program, the development of technology to use low-enriched uranium (LEU) for production of the fission product {sup 99}Mo has continued. Progress in fabrication development and out-of-pile thermal testing of targets based on uranium metal foils is summarized. Uranium foil of 125 {mu}m (0.005 in.) thickness has been fabricated. Heat treatments have been developed to provide a random crystal structure, which is required for satisfactory irradiation properties. Two target designs, a tapered thermal expansion type and a split-outer-tube type, are presented. After anionic coating and thermal treatment of prototypical targets, no diffusional or dimensional changes were observed. A formal agreement for cooperation between Argonne National Laboratory (ANL) and the Indonesian National Atomic Energy Agency (BATAN) for irradiation testing is in the final stage of negotiation. The first irradiation tests of targets fabricated by ANL are scheduled to begin during the first half of 1995.

Between 1950 and 1970, scientific ballooning achieved many new objectives and made a substantial contribution to understanding near-earth and space environments. In 1986, the Lawrence Livermore National Laboratory (LLNL) began development of ballooning technology capable of addressing issues associated with precision tracking of ballistic missiles. In 1993, the Radar Ocean Imaging Project identified the need for a low altitude (1 km) airborne platform for its Radar system. These two technologies and experience base have been merged with the acquisition of government surplus Aerostats by Lawrence Livermore National Laboratory. The CALIOPE and TAISIR Programs can benefit directly from this technology by using the Aerostat as an experiment platform for measurements of the spill facility at NTS.

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Experimental studies are under way at the Oak Ridge National Laboratory (ORNL) which are designed to measure the time evolution, ionization efficiencies, and release efficiencies of implanted elements diffused from refractory target materials which are candidates for forming radioactive ion beams (RIBs) at the Holifield Radioactive Ion Beam Facility (HRIBF). The diffusion coefficients are derived by comparing experimental data with numerical solutions to a one-dimensional form of Fick`s second law for ion implanted distributions. In this report, we describe the experimental arrangement and provide time release data and diffusion coefficients for releasing ion implanted Cl from Zr{sub 5}Si{sub 3} and {sup 75}As, {sup 79}Br, and {sup 78}Se from Zr{sub 5}Ge{sub 3}.

The authors have begun to develop a novel technique for active neutron assay of fissile material in spent nuclear fuel. They are using a Schlumberger neutron generator for the direct measurement of the fissile material content in spent fuel, in place of the indirect measures used at present. The technique they are investigating is termed synchronous active neutron detection (SAND). It closely follows a method that has been used routinely in other branches of physics for the detection of very small signals in the presence of large backgrounds. Synchronous detection instruments are widely available commercially and are termed ``lock-in`` amplifiers. They have implemented a digital lock-in amplifier in conjunction with the Schlumberger neutron generator to explore the possibility of synchronous detection with active neutrons. The results to data are preliminary but quite promising. The system is capable of resolving the fissile material contained in a small fraction of the fuel rods in a cold fuel assembly. It also appears to be quite resilient to background neutron interference.

In the P865 Letter of Intent, we have proposed a fixed-target experiment aimed at achieving high sensitivity to decays both of charm and of beauty. I describe here a revised version which is somewhat more optimized for charm and less so for beauty. The rationale for this change of emphasis is two-fold: by the time a new fixed-target experiment might run ({approx} Year 2000), it is likely that studies of beauty at the level proposed in P865 win no longer be competitive; furthermore, it may well be that charm is even more interesting than beauty since the background to rare processes beyond the Standard Model is so much smaller in charm than in beauty. At this workshop, Pakvasa has emphasized that rare and forbidden processes such as D{sup o} mixing, charm-changing neutral currents, and lepton-family-violating currents must exist at some level if we are ever to have an understanding of the fermion masses and mixings; some extensions of the Standard Model predict effects detectable at the level of sensitivity discussed here.

The positron lifetimes of two organic superconductors, {kappa}-(ET){sub 2}Cu(NCS){sub 2} and {kappa}-(ET){sub 2}Cu[N(CN){sub 2}]Br, are measured as a function of temperature across {Tc}. A drop of positron lifetime below {Tc} is observed. Positron-electron momentum densities are measured by using 2D-ACAR to search for the Fermi surface in {kappa}-(ET){sub 2}Cu[N(CN){sub 2}]Br. Positron density distributions and positron-electron overlaps are calculated by using the orthogonalized linear combination atomic orbital (OLCAO) method to interprete the temperature dependence due to the local charge transfer which is inferred to relate to the superconducting transition. 2D-ACAR results in {kappa}-(ET){sub 2}Cu[N(CN){sub 2}]Br are compared with theoretical band calculations based on a first-principles local density approximation. Importance of performing accurate band calculations for the interpretation of positron annihilation data is emphasized.

Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE`s Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC`s NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and …