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Recent DIII?D experiments show that ideal kink-modes can be stabilized at high beta by a resistive wall, with sufficient plasma rotation. However, the resonant response to static magnetic field asymmetries by a marginally stable resistive wall mode can lead to strong damping of the rotation. Careful reduction of such asymmetries has allowed plasmas with beta well above the ideal MHD no-wall limit, and approaching the ideal-wall limit, to be sustained for durations exceeding 1?s. Feedback control can improve plasma stability by direct stabilization of the resistive wall mode or by reducing magnetic field asymmetry. Assisted by plasma rotation, direct feedback control of resistive wall modes with growth rates more than five times faster than the characteristic wall time has been observed. These results open a new regime of tokamak operation above the free-boundary stability limit, accessible by a combination of plasma rotation and feedback control.

Neutron cameras with horizontal and vertical views have been designed for ITER, based on systems used on JET and TFTR. The cameras consist of fan-shaped arrays of collimated flight tubes, with suitably chosen detectors situated outside the biological shield. The sight lines view the ITER plasma through slots in the shield blanket and penetrate the vacuum vessel, cryostat, and biological shield through stainless steel windows. This paper analyzes the expected performance of several neutron camera arrangements for ITER. In addition to the reference designs, the authors examine proposed compact cameras, in which neutron fluxes are inferred from {sup 16}N decay gammas in dedicated flowing water loops, and conventional cameras with fewer sight lines and more limited fields of view than in the reference designs. It is shown that the spatial sampling provided by the reference designs is sufficient to satisfy target measurement requirements and that some reduction in field of view may be permissible. The accuracy of measurements with {sup 16}N-based compact cameras is not yet established, and they fail to satisfy requirements for parameter range and time resolution by large margins.

The deuterium-tritium (D-T) experimental program on the Tokamak Fusion Test Reactor (TFTR) is underway and routine tritium operations have been established. The technology upgrades made to the TFTR facility have been demonstrated to be sufficient for supporting both operations and maintenance for an extended D-T campaign. To date fusion power has been increased to {approximately}9 MW and several physics results of importance to the D-T reactor regime have been obtained: electron temperature, ion temperature, and plasma stored energy all increase substantially in the D-T regime relative to the D-D regime at the same neutral beam power and comparable limiter conditioning; possible alpha electron heating is indicated and energy confinement improvement with average ion mass is observed; and alpha particle losses appear to be classical with no evidence of TAE mode activity up to the P{sub FUS} {approximately}6 MW level. Instability in the TAE mode frequency range has been observed at P{sub FUS} > 7 MW and its effect on performance is under investigation. Preparations are underway to enhance the alpha particle density further by increasing fusion power and by extending the neutral beam pulse length to permit alpha particle effects of relevance to the ITER regime to be more fullymore » explored.« less

DuP 996, 3,3-bis(4-pyrindinylmethyl)-1-phenylindolin-2-one, physostigmine (PH), tetrahydroaminoacridine (THA) and 3,4-diaminopyridine (3,4-DAP) were compared for their ability to protect against hypoxia-induced performance deficits in a passive avoidance (PA) task. The ability to retain PA response was found to decrease as the oxygen concentration decreased with the largest retention deficit occurring at 6.5% oxygen. DuP 996 (0.01-0.1 mg/kg SC), 3,4-DAP (0.1-10.0 mg/kg SC), THA (0.3-5.0 mg/kg SC) and PH (0.001-0.1 mg/kg SC) administered one minute after PA training produced dose-dependent increases in retention latencies following exposure to 6.5% oxygen. In comparing each compound for side effects, DuP 996 induced tremor and mortality at 10 and 40 mg/kg SC, respectively, and PH at 0.3 and 0.8 mg/kg SC, respectively. With PH the 0.3 mg/kg SC dose also produced hypersalivation and a decrease in lift strength. THA produced tremor and mortality at 6.0 and 40 mg/kg SC, respectively, and 3,4-DAP at 50 and 200 mg/kg SC, respectively. 3,4-DAP also produced chromodacryorrhea and hypersalivation at 50 mg/kg SC. Dividing the dose necessary to produce mortality by the highest effective dose active in the hypoxia test yielded a safety ratio for DuP 996 of 400, for 3,4-DAP 20, for PH 8, and for THA 8, showing a greater safety margin for DuP 996 than the other cholinergic agents. These results suggest that DuP 996 may be of use in the treatment of diseases associated with cognitive impairment and may have a greater safety margin than other cholinergic agents.

The diagnostic instrumentation on TFTR (Tokamak Fusion Test Reactor) and the specific properties of each diagnostic, i.e., number of channels, time resolution, wavelength range, etc., are summarized in tables, grouped according to the plasma parameter measured. For comparison, the equivalent diagnostic capabilities of JET (Joint European Torus) and the Japanese large tokamak, JT-60, as of late 1987 are also listed in the tables. Extensive references are given to publications on each instrument.

We report results of the TFTR fission detector calibration performed in December 1988. A NBS-traceable, remotely controlled {sup 252}Cf neutron source was moved toroidally through the TFTR vacuum vessel. Detection efficiencies for two {sup 235}U detectors were measured for 930 locations of the neutron point source in toroidal scans at 16 different major radii and vertical heights. These scans effectively simulated the volume-distributed plasma neutron source, and the volume-integrated detection efficiency was found to be insensitive to plasma position. The Campbell mode is useful due to its large overlap with the count rate mode and large dynamic range. The resulting absolute plasma neutron source calibration has an uncertainty of {plus minus} 13%. 21 refs., 23 figs., 4 tabs.

In ST Tokamak discharges with hydrogen or helium as the working gas the measured plasma resistance is usually found to be slight but consistently larger (1.1-1.5 times) than the resistance calculated from measured electron temperature and ionic charge radial profiles. The discrepancy has been ascribed tentatively to undetected high-Z material (Mo or W) from the aperture limiter. Recent experiments with neon, with effective ionic charge Z=9-10 in the discharge, do show good agreement between measured and calculated resistance. In other respects the behaviour of the neon discharge differs only slightly and in the expected direction from hydrogen or helium discharges: larger power input, higher electron temperature, and higher radiation losses. Also, measurement of the intensities of the recently discovered resonance lines of Mo XIII and Mo XIV do indicate a molybdenum concentration in the discharges of the ST Tokamak that is adequate to account for the above mentioned discrepancies in the resistance of H and He plasmas.

A detailed description of the time behaviour of a hydrogen discharge in the ST-Tokamak is based on measured radial electron temperature and density profiles at 12 different times, together with measurements of the Ohmic-heating current and voltage, the temporal, spatial, and spectral distributions of hydrogen light, the ion temperatures, and impurity concentrations. Early in the discharge the electron temperature profiles show evidence of a skin effect that develops on a time-scale of several milliseconds into a peaked profile of about 2.2 keV maximum. Thereafter the peak temperature stops growing and develops into a flat plateau, the width of which appears to be determined by the Kruskal-Shafranov limit. The average particle confinement time scales with , and reaches a maximum of 13-14 ms. The power balance is dominated by electron loss and re-cycling, rather than ion loss or radiation. The recycling process at the aperture limiter appears to involve sufficiently energetic neutral atoms to provide a fairly flat radial source function for particles, and hence to influence directly the development of the radial distribution of power input and energy balance.

Transition rate equations for atomic hydrogen are solved to obtain coefficients for population of excited levels and for ionization and recombination. The results are based upon more accurate transition rates, cover a wider range of plasma parameters, and are obtained by a more general solution of the rate equations than previously available compilations. Diagnostic applications for laboratory plasmas are discussed.

The definition of passive smoking used by T. Hirayama [ Brit. Med. J. 282 , 183–185 (1981)] and other authors has at least three major shortcomings: it is only applicable to a highly selective sub-population; varying lifestyle patterns cannot be taken into account; and exposure outside the home is neglected. To overcome these shortcomings, a preliminary qualitative and classificatory definition of passive smoking that includes the total population as well as any smoke exposure, regardless of its location, was developed. This definition does not include the quantity of exposure or changes over time. Based on a representative survey, 17.8% of the population over 35 years are potential passive smokers according to this definition. The questionnaire developed by E. L. Wynder and associates (American Health Foundation, New York) presents difficulties in scoring the results for different lifestyles. Therefore a quantitative concept was developed for estimating exposure over any period of time as a generalized assessment instrument. The concept of maximum exposed M-time for an individual ( T I M ) as well as for a group ( T G M ) is introduced. The results are presented graphically by a cumulative standardized exposed M-time diagram. Results obtained so far lean toward plausibility and stability of the data and the concept. The interview form has still to be validated.

In this research, a quantitative study of the EEG from 5 subjects permitted a detailed analysis of the effect of 30 mg of flurazepam administered over 7 nights. Four placebo baseline nights and 3 placebo withdrawal nights were also recorded. For 4 of the subjects, a nondrug and nonplacebo follow-up record was obtained 4 to 6 weeks later. The subjects were 4 females, 1 male, age range 23-42. All complained of either sleep onset greater than 45 min, sleep length of less than 6 h, or two or more sleep awakenings. Compressed spectral analysis yielded a computer-generated somnogram on each of the 15 nights of sleep, and an automated spindle detector was used to count and measure the duration of spindle bursts with frequencies of 12.25-15.5 c/sec on baseline nights 3 and 4, drug nights 1, 2, 3 and 7, on the 3rd withdrawal night, and on the 4-6 week followup record. K-complexes were scored visually on the 4th baseline and 7th drug nights. There were no significant differences in spindle rate per minute among baseline nights and the follow-up record. By the 2nd drug night, spindle rate had significantly increased over the baseline rate. Linear contrast analysis indicated there was a significant increase of spindle rate over drug nights. All 5 subjects showed this pattern of increase. In contrast to the increase in spindle activity, the rate per minute of K-complexes significantly decreased during drug administration.

A narrow line optically pumped D/sub 2/O laser operating at 385 ..mu..m has delivered more than 5 J in pulses longer than 3 ..mu..sec using a large aperture unstable resonator cavity design. Pulse levels which are > 1 J and 1 ..mu..sec are necessary for a single shot ion temperature measurement by Thomson scattering in large tokamaks. Experiments have, for the most part, been conducted at a 360 J, 5 ..mu..sec CO/sub 2/ laser pump level where high efficiency (approx. 2.5 J at 385 ..mu..m) has been obtained. These are the highest energies reported to date in the far infrared. In addition, the pulse length has been extended beyond the vibrational relaxation time.

Release of human growth hormone (HGH) has been shown to occur during normal undisturbed sleep.1,2,3 We have also demonstrated in our laboratory that this release is related to the physiologic state of sleep itself and is not dependent of an inherent circadian rhythm.4 Finally, we have demonstrated that release of HGH is correlated with that portion of sleep cycles showing slow, synchronized electroencephalographic activity.4 We now report results of an attempt to deprive subjects of EEG stages 3 and 4,5 referred to as slow wave sleep (SWS), to test the effect of this deprivation on release of HGH in sleep. The data suggest that deprivation of SWS results in diminished and delayed secretion of HGH in sleep.