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This paper reports the magnetic and magneto-optical properties of antiferromagnetic exchange coupled (AFC) RE-TM double layered films prepared by sputter deposition. The sample structure is glass/underlayer Ru/Gd-Fe-Co/(E-layer Fe-Co)/AFC layer Ru/(E-layer Fe-Co)/Gd-Fe-Co/protectivelayer Ru. The exchange coupling energy J was found to depend on Ru thickness of the AFC layer. The first AFC peak was found at an AFC layer thickness of 3.0 A. Next we inserted a thin Fe-Co layer called the “E-layer,” between the AFC layer and the magnetic layer to improve the J value. In AFC RE-TM double layered films, a complicated Kerr loop was observed when each magnetic layer was thin. Then we compared the calculated result with the experimental result to distinguish the ferromagnetic coupling from the AFC. Next we investigated thermal stability of J. Moreover we calculated the magneto-optical properties with the film structure of DWDD, using AFC RE-TM double layered films for the displacement layer.

The electron cyclotron range of frequency (ECRF) system was designed and operated on the JT-60U to locally heat and control plasmas. The frequency of 110 GHz was adopted to inject the fundamental O-mode from the low field side with an oblique injection angle. The system is composed of four 1 MW-level gyrotrons, four transmission lines, and two antennae. The gyrotron is featured by a collector potential depression (CPD) and a gaussian beam output through a diamond window. The CPD enables JAERI to drive the gyrotron under the condition of the main DC voltage of 60 kV without a thyristor regulation. The gaussian mode from the gyrotron is effectively transformed to HE{sub 11} mode in the 31.75 mm diameter corrugated waveguide. About 75% of the output power of the gyrotrons can be injected into plasmas through the waveguides about 60 m in length. There are two antennae to control the deposition position of the EC wave during a plasma discharge. One is connected with three RF lines to steer the EC beams in the poloidal direction. The other is to control the EC beam in the toroidal and poloidal directions by two steerable mirrors.On the operation in 2000, the power ofmore » 1.5 to 1.6 MW for 3 s was successfully injected into plasmas using three gyrotrons. Local profile control was demonstrated by using the antennae. This capability was devoted to improve the plasma performance such as high T{sub e} production more than 15 keV and suppression of the MHD activities. In 2001, the fourth gyrotron, whose structure was improved for long pulse operation, has been installed for a total injection power of {approx}3 MW.« less

Review on MINA (MYC induced nuclear antigen), with data on DNA, on the protein encoded, and where the gene is implicated.

A superconducting magnet system was designed and fabricated for a 1-MW gyrotron in a frequency range of 110-140 GHz. The system consists of superconducting magnets, a cryostat, a two-stage cooler, and power supplies. The diameter of the gyrotron bore is 220 mm. A magnetic field of 5.0 T in the resonance region was obtained with a 340-mm bore superconducting split coil. A magnetic field of 0.25 T in the gun region was obtained with two solenoid coils. A persistent current switch, removable current leads, and a two-stage cooler were adopted to decrease the heat load of liquid helium. The superconducting magnet system has successfully achieved a 110% rated current without quenching. >

The electron gun of the 1 MW-klystron for JT-60 was redesigned to suppress the degradation of the withstand voltage due to deterioration with age. The key aims were to reduce the concentration of the electric field near the electrodes by improving the configuration of the electrodes, and to suppress the barium evaporation from the cathode by replacing the non-metal-coated dispenser cathode (S-type) with an iridium (Ir)-coated one allowing a iower operating temperature. The maximum beam operating voltage was inereased from 84 kV to 94 kV and an RF output power of 1.4 MW was generated for 10 sec at 2.17 GHz. Preliminary results of the klystron operation in JT-60 experiments showed that DC breakdown frequency of the improved klystron was reduced to less than 10% of the previous one.

The aim of this paper is to develop a short version of the Japanese OHIP (OHIP-J) appropriate for use in young and middle-aged adults, and to evaluate its properties using cross-sectional data.A study population of 8,658 workers aged 20-59 years rated their oral health by means of a self-administered questionnaire. Using a factor analysis approach, a shortened version of OHIP-J was derived. Internal consistency, floor effect, and construct validity were determined.We derived a subset of 18 items from OHIP-J (OHIP-JA18), grouped into four subscales: "functional limitation", "physical pain", "psychological discomfort", and "disabilityhandicap". All four subscales had acceptable internal consistency (Cronbach alpha0.79). OHIP-JA18 demonstrated an acceptable floor effect, which was determined by the proportion of subjects who obtained a 0 score (30%); however, the floor effect of the ordinary shortened version based on OHIP-14 (OHIP-J14) was not acceptable. We confirmed the conceptual framework of OHIP-JA18 that "disabilityhandicap" is affected by "functional limitation", "physical pain" and "psychological discomfort", because the model fitted the data moderately well by structural equation modeling (SEM) analysis (GFI = 0.90, RMSEA = 0.08).OHIP-JA18 demonstrated acceptable measurement parameters to justify its use in outcome assessment for oral health related quality of life (OHQOL) in young and middle-aged adults in Japanese workers. Further studies will be needed to evaluate an intervention such as worksite health promotion.

Recent lower hybrid current drive (LHCD), and heating (LHH) experiments on JT-60 are reported. The current drive product of neRpIRF approximately 12.5*1019 m-2 MA was achieved at the LH power of approximately 4.5 MW, and the CD efficiency, the energy confinement, the global power balance and the heat load on divertor plates were investigated in high power LHCD plasmas. Nearly steady state H-mode discharges were found during LHCD with two different frequency injections. Sawtooth suppression in NB heated plasmas by LHCD have shown an improvement in confinement near the plasma center. Parametric instabilities in LH heating experiments were significantly reduced by increasing the plasma current, and the stored energy increased linearly with heating power of up to approximately 9 MW at ne approximately 7*1019 m-3 and Ip=2.75 MA. Parametric instabilities near the plasma edge in the ion heating regime were also reduced in peaked density plasmas produced by pellet injection and LH waves increased the central plasma pressure at ne(0) > 1.4*1020 m-3.

Imprint lithography has been included on the ITRS Lithography Roadmap at the 32 and 22 nm nodes. Step and Flash Imprint Lithography (S-FIL TM ) is a unique method for printing sub-100 nm geometries. Relative to other imprinting processes S-FIL has the advantage that the template is transparent, thereby facilitating conventional overlay techniques. Further, S-FIL provides sub-100 nm feature resolution without the significant expense of multi-element, high quality projection optics or advanced illumination sources. However, since the technology is 1X, it is critical to address the infrastructure associated with the fabrication of templates. With respect to inspection, although defects as small as 70 nm have been detected using optical techniques, it is clear that it will be necessary to take advantage of the resolution capabilities of electron beam inspection techniques. The challenge is in inspecting templates composed purely of fused silica. This paper reports the inspection of both fused silica wafers and plates. The die-to-database inspection of the wafers was performed on an NGR2100 inspection system. Fused silica plates were inspected using an NGR4000 system. Three different experiments were performed. In the first study, Metal 1 and Logic patterns as small as 40 nm were patterned on a 200 mm fused silica wafer. The patterns were inspected using an NGR2100 die-to-database inspection system. In the second experiment, a 6025 fused silica plate was employed. Patterns with a limited field of view (FOV) were inspected using an NGR4000 reticle-based system. To test the tool's capability for larger FOVs, 16 × 16 μm areas on a MoSi half tone plate were scanned and stitched together to evaluate the tool's ability to reliably do die-to-database comparisons across larger inspection areas.

The sixth complement component (C6) has a common charge polymorphism, C6A and C6B, with similar gene frequencies in all major populations. In addition, C6B2 is also found in Japanese populations at a frequency of about 6%. Sequence analyses of the coding region of three human and ape C6 alleles indicated four nonsynonymous and three synonymous changes in C6*B2 relative to C6*A, suggesting that a recombination event occurred between C6*B2 and C6*A to give rise to C6*B. Sequence variation in a 3.86 kb region encompassing exon 3, where the causal base change of the common C6 polymorphism is found, indicated that several single nucleotide polymorphisms (SNPs) were in extensive linkage disequilibrium (LD), with little differentiation among populations. Sliding window estimates of two test statistics for neutrality revealed significant values in a subregion where the replacement coding polymorphism resides, in all three human populations. These results raise the possibility that the two common C6 alleles in human populations are maintained by balancing selection.

We have investigated the genetic basis for the Hp0 phenotype amongst 123 randomly selected Ghanaians. A total of 17 individuals were determined to be Hp0 phenotype, based on the classical method for Hp phenotyping of Hb-supplemented plasma. Out of the 17 Hp0 individuals, nine subjects were further classified as ahaptoglobinaemic and eight as hypohaptoglobinaemic by Western blots and double immunodiffusion. We identified three previously known base substitutions (A-55G, A-61C and T-104A) and three new ones (C-101G, T-191G and C-242T) within the 5' flanking region of the Hp gene. The A-61C base substitution significantly decreased transcriptional activity and was associated strongly with Hp2 allele and ahaptoglobinaemia. The C-101G substitution was similar in transcriptional activity to the wild-type and was associated with Hp1S allele and hypohaptoglobinaemia. The Hpdel allele seen in Asian populations was absent. We conclude that the Hp0 phenotype in Ghana has a genetic basis that differs significantly from that seen in Asia.

A high power and long pulse gyrotron development has been carried out in JAERI for fusion application. The frequency is 170 GHz for ITER (International Thermonuclear Experiment Reactor) and 110 GHz for JT-60U tokamak of JAERI. Both gyrotrons have low loss diamond window. The outputs of 0.9 MW/9.2 sec and 0.5 MW/30 sec were demonstrated at 170 GHz with a depressed collector operation. It was proved that a pulse extension is possible without long time conditioning in principle. On 110 GHz gyrotron, 1.2 MW/4s ec and 1 MW/5 sec operation have been accomplished in the heating experiment of JT-60U.

This paper describes the operation and control for the 110 GHz ECRF system for JT-60U, which has started operation since March in 1999. This system is composed of a 1 MW gyrotron, its high voltage power supply, a transmission line about 60 m in length and a quasi-optical antenna using a steerable mirror. Key issues of the ECRF system are to drive the gyrotron stably and to control the local RF deposition profile in a plasma.

A design concept for an RF power supply using DC-DC converters without large filter capacitors and crowbar circuits is proposed. The RF power supply is designed to yield smooth voltage and, fast turn-off and turn-on output characteristics. System simulation and a small experimental model confirm these qualities. A 2-MW (-100 kV, 20-A) power-supply design is introduced, and its realization and total efficiency are also discussed. >

A monolithic low-noise and low-distortion mixer-oscillator IC has been developed for miniaturized coilless broadcasting satellite TV tuners. In order to obtain a high IP3 and low noise figure (NF), apportionment of gain and dynamic range in each circuit block were optimized. The fabricated IC, by using a newly developed asymmetric self-aligned LDD FET process, showed a conversion gain of 16.5 approximately 18.1 dB, a NF of 6.8 approximately 7.6 dB, and an IP3 of 23 approximately 25 dBm over the frequencies from 900 to 2000 MHz. >

A design and experimental results of a 110 GHz gyrotron with a single stage depressed collector are presented. By recovering a spent beam energy, efficiency of the gyrotron was improved from 30% to 50% with the RF output power of 610 kW and the pulse duration of 50 ms. A stable 5 sec oscillation was performed at 350 kW (output energy 1.75 MJ) with high efficiency of /spl sim/48% and the 420 kW-3.3 sec oscillation was also obtained. Conditioning time was short compared with the conventional gyrotron since a collector heat load was significantly reduced by the application of the beam retarding voltage. >

The authors report on the design and test results of the JAERI gyrotron test facility at Naka which was originally intended for testing the high-power klystron. The AC GTO (gate turn-off thyristor) switch, the series regulator tube, and the high-speed protection system are applied for the power supply system. The AC GTO switch is able to break the current of 4500 A without any damaging surge voltage. The switch is also able to control the DC output voltage within +or-5% at the cathode voltage of the regulator tube. The series regulator tube system is able to rise within 200 mu s and keeps the flat-top voltage within +or-0.13% at the cathode voltage of -80 kV for 1 ms. The high-speed interlock system realizes turn-off performance of 6 mu s and a reliable and safe operation of the gyrotron. The authors have demonstrated the operation of 440 kW during 1 ms using a short pulse gyrotron at 120 GHz. >

The high order mode escalation which reduces the heat load at the cavity of 170 GHz has succeeded without the adjacent mode competition. We performed 0.5 MW-0.75 sec and 0.175 MW-10 sec oscillation, but the output power was limited by the gyrotron window. For this solution, we have lately confirmed that the large size window disk of diamond manufactured by chemical vapor deposition (CVD) has the outstanding property; low loss tangent (tan/spl delta//spl les/1.4/spl times/10/sup -4/) and high thermal conductivity (1800 W m/sup -1/ K/sup -1/) and is available for 0.5 MW continuous wave (cw) transmission. On the basis of the result above, the modified 170 GHz 0.5 MW, long pulse gyrotron with the diamond window has been fabricated. We will also construct the 100 GHz range transmission line and the high power (1 MW level) and long pulse transmission experiment will be carried out.

The ECH system is under consideration to heat plasma and drive plasma current locally for JT-60SU. On the first stage, the frequency of 110 GHz is proposed to inject the fundamental O-mode wave at the toroidal field of 4T. The system design is intended to operate at a pulse length of 10 second with output power of 4 MW, because the design priority is to use the existing RF facility of JT-60 such as the DC power supply within 10 second operation. On the second stage, the steady state operation will be done incorporating 170 GHz and 1 MW gyrotron at the full toroidal magnetic field of 6T by employing a steady state DC power supply. A high power up to 50 MW is generated by fifty gyrotrons. A large antenna which is composed of an array of fifty corrugated waveguides is designed to operate with a good radiation shield against the neutrons from plasmas.

A status of high power gyrotron development at JAERI is presented. Gyrotrons of 170 GHz and 110 GHz are under development for ITER (International Thermonuclear Experimental Reactor) and JT-60U, respectively. Both gyrotrons have a low loss synthetic diamond window that enables Gaussian beam output over 1 MW and a depressed collector. The output power of -1 MW/3 s was obtained for the 110 GHz gyrotron. A heating experiment was carried out using three 110 GHz gyrotrons on the JT-60U, and an effective local heating capability in plasma was demonstrated (e.g., attainment of 15 keV of electron temperature). As for 170 GHz device, an output power of 1.2 MW with electron beam of 85 kV/49 A was obtained for a short pulse (/spl sim/5 ms). The efficiency of /spl sim/52% was obtained at 1.0 MW with a depressed collector operation of 36.5 kV.

Recently, the JT-60U has employed ECRF system in addition to LHCD and ICRF systems. Three types of RF experiments on JT-60U have been performed. A reversed magnetic shear (R/S) configuration with internal transport barrier (ITB) was successfully maintained for 4.7 s in a quasi-steady state by LHCD in addition to the bootstrap current, where all profiles of temperature and plasma current were almost stationary. On the normal operation without heating during plasma current ramp-up, high electron temperature (Te0∼10 keV) with a strongly peaked profile was produced by LHCD alone at the density of ∼0.5×1019 m−3. This peaked temperature profile was featured by a reduction in core density. The central electron temperature and density slowly changed in several seconds. The performances of ICRF (2ωCH) on the R/S configuration were also studied. Degradation of confinement of energetic particles was observed probably due to the large banana orbit loss. An 110 GHz ECRF system has been operated on JT-60U. Its gyrotron has successfully generated power at the level of up to 830 kW for 300 ms and is under conditioning. On the initial operation, the power of 620 kW was injected into plasmas. The central electron temperature increased from 3 keV to 5.5 keV at ne∼0.6×1019 m−3. A controllability of local heating was also demonstrated by the poloidally steerable mirror.

A digital TV tomography system, capable of retrospective reconstruction of multiple digital tomographic images, has been developed and its basic physical characteristics have been evaluated. The multiple tomographic images were formed through retrospective reconstruction of digital data acquired on a linear tomographic x-ray unit and an image intensifier-television system. Digital data were obtained with a series of 30 pulsed exposures during linear motion of the system. A distortion correction algorithm for the convex surface of the image intensifier was developed in order to reduce image distortion. A phantom study showed that the square-wave response at the fulcrum plane was slightly inferior to that in conventional tomography. There was also a slight decrease in the square-wave response away from the fulcrum plane and upon application of a correction algorithm, as compared with the response of the original reconstructed image at the fulcrum plane. The exposure dose for a single image was approximately half that in conventional tomography. Because of many advantages, including low exposure, short examination time, digital image manipulation, and applicability to picture archiving and communication systems, this is likely to become an important method in radiology when further technical refinements have been made.

A unit for digital TV tomography (DTT) was constructed on the basis of retrospective reconstruction of digital data acquired during a linear tomographic motion of an X-ray tube and an image intensifier with a television camera (I.I.-TV) assembly. Following descriptions of the basic principle and system, clinical results obtained with this unit are presented. Comparison with conventional tomography of the chest, skull, abdomen, and bones and joints showed equal diagnostic information in more than 50% of cases. Application to intra-arterial and intravenous DSA provided excellent images, but no new information was obtained. DTT has the advantages of technical simplicity, short examination time, low exposure dose, and compatibility with a PACS system. This technique will become an important part of a modern radiology department.

Emphases in JT-60 experiments are placed on (1) lower-hybrid (LH) current drive characteristics with a multi-junction type launcher, and (2) the confinement study with combination of neutral beam injection LH current drive and pellet injection. The new multi-junction LH launcher provides a sharp N/sub /// spectrum with high directivity for N/sub ///=1-3.4. The current drive efficiency and the radial distribution of high energy electron production show clear correlation with injected N/sub ///: the current drive efficiency has the maximum at low N/sub ///( approximately 1.3) while flattening of plasma current is more effective in large N/sub ///. A broad radial distribution of high energy electron current and approximately 30% reduction in sawtooth inversion radius were obtained by high N/sub /// ( approximately 2.5) LH injection. To fully suppress the sawtooth activity, low N/sub /// ( approximately 1.3) injection was found to be more effective. Improved energy confinement has been obtained with hydrogen pellet injection. Energy confinement time was enhanced up to 40% relative to usual gas fuelled discharges. The discharge has a strongly peaked electron density profile with ne(0)/(ne) approximately 5 and ne(0) approximately 2.0*1020 m-3. The improved discharges are characterized by a strongly peaked pressure profile within the q=1 magnetic surface, and degrades when a large sawtooth recovers or the pressure gradient may reach a critical value. When large (3 mm, 4 mm) and fast (2.2 km/s) pellets were injected, 30% energy confinement improvement was obtained even during the NB heating of 14 MW. Further investigations of IDC characteristics have been made. The oxygen impurity lines from the main plasma and the main radiative loss drop first. Then the plasma stored energy starts to rise. The particle recycling is reduced around the main plasma, and is localized in the neighborhood of the X-point with a time lag of approximately 0.2 sec. Eventually the discharge shows a significant remote radiative cooling power at the divertor region.

Initial ohmic heating experiments in JT-60 were performed for a three month period of April-June 1985. A maximum plasma current of 1.6 MA was obtained for both divertor and limiter discharges. Low-q discharges of qeff=2.5 and high density discharges of 4.8*1019 m-3 in line-averaged density were obtained in the divertor configuration. In divertor discharges radiated loss from the main plasma can be kept at 20-30% of the ohmic input.

Essential divertor functions — density and energy control — have been investigated in the JT-60 divertor with metal walls. Neutral pressure in the divertor chamber increases in proportion to n2e and high recycling state for particle exhaust is realized. At ne ≤ 6 × 1019m−3, wall pumping by the divertor plates is dominant in particle exhaust. However, at ne ≥ 6 × 1019m−3, particle exhaust by active divertor pumping systems becomes essential. Because of the effectiveness of the divertor, radiation loss in the main plasma is reduced to 5–10% of the absorbed power and impurity concentrations are significantly suppressed at very low level (Zeff = 1.5-2.0). In the experiments with graphite walls, short periods of H-mode phases were found in the outside X-point divertor discharges although improvement in energy confinement is limited to within 10%. In limiter discharges, combination of high vessel temperature (210–300 °C) and low current limiter discharges (1.5 MA) without gas puffing is effective as a wall conditioning in obtaining reproducible high density discharges. The maximum parameters, Ip = 3.2 MA, ne = 1.2 × 1020m−3, qeff = 2.2 at Bt = 4.8T, a Murakami parameter of 7.5, and a stored energy of 3.1 MJ have been attained. The maximum density is limited by the occurence of the MARFE. During high power neutral beam heating, enhanced carbon influx was observed possibly due to chemical sputtering. The wall pumping by the inner wall is still effective in decreasing the electron density from the high density region of ne ~ 1 × 1020m−3. An empirical energy confinement scaling of JT-60 has been drawn in terms of an offset linear function as τE = 0.19 I1.9PPabs + 0.062 a1.8p

From June to October 1987, JT-60 achieved fusion product (ne(0). tau E*.Ti(0)) of 6*1019 m-3.keV.s with hydrogen plasma at plasma current of 2.8 to 3.1 MA with neutral beam power of approximately 20 MW. The central electron density of 1.3*1020 m-3 was obtained at plasma current of 3 MA with 13 approximately 20 MW neutral beam power and the confinement time reached 0.14-0.18 s. An offset linear scaling law like the Shimomura-Odajima scaling on confinement time will be able to reproduce experimental data better than that of the Goldston type scaling. With low beam energy injection approximately 40 keV, confinement degradation was found. Many short periods (0.05 approximately 0.1 s) of H-mode phase were found in outside X-point divertor discharges with NB or NB+RF(LH or IC) heating power above 16 MW. However, improvement in energy confinement time was limited to 10 %. The ballooning/interchange stability analyses were also made for the outside X-point divertor equilibrium in connection with H0-phase capability. Heating powers of 9.5 MW and 1.9 MW were obtained by LHRF, ICRF injection, respectively. In combined LHRF and NB heating, the incremental energy confinement time of 0.064 s was obtained, which is the same level of that of NB heating only. In combined NB and on-axis ICRF heating of low ne discharge, an incremental energy confinement time of 0.21 s was obtained, which is three times as long as those of NB or ICRF heating only. High energy beam ions were accelerated by ICRF in the central region of the plasma.

In the last year, ohmic heating experiments were performed in JT-60 for about three months; May–June 1985 and March 1986. The major experimental effort has been concentrated on the divertor configuration in anticipation of H-mode operation of JT-60 in high power supplementary heating experiments starting in August 1986. Stable discharges with a divertor have been obtained at Ip = 1.85 MA and ne = 5.7 × 1019m−3. Radiated power from the main plasma in divertor discharges is reduced to one third of that in material limiter discharges. The electron density has a broad radial profile and the effective safety reaches qeff = 2.5. The neutral gas pressure in the divertor chamber becomes significantly high and the control of particle recycling has been attempted.

Results are presented of the first Lower Hybrid Current Drive (LHCD) experiments in JT-60. 2 MA of RF driven current is successfully produced for the first time in a reactor grade tokamak. The magnetic divertor works quite well in eliminating the impurities released by the current carrying fast electrons which have allowed the generation of the reactor relevant RF current in a very low density plasma. The efficiency which is defined as ηCD = eRIRF/PLH(1019 m−3 AW−1), reaches values of 0.8 to 1.7. NBI heating enhances the current drive efficiency by a factor of 1.5, and LHCD improves the confinement time of high power NBI heated plasma. The key to confinement improvement is found to be the active control of the current profile by LHCD.

Non-histone chromosomal protein high mobility group 1 (HMG-1) rapidly migrates into the nucleus when injected into the cytoplasm of bovine fibroblasts and HeLa cells by red cell-mediated microinjection (Rechsteiner, M., and Kuehl, L. (1979) Cell 16, 901-908). We isolated hybridomas secreting monoclonal antibodies against HMG-1. One of these monoclonal antibodies, FR-1, inhibited in vitro binding of 125I-HMG-1 to chromatin isolated from FL cells. When 125I-HMG-1 was co-introduced with antibody FR-1 by red cell-mediated microinjection, antibody FR-1 did not prevent the accumulation of 125I-HMG-1 in the nucleus. When 125I-antibody FR-1 or fluorescein isothiocyanate antibody FR-1 was introduced into the cytoplasm of FL cells, most of the antibody did not accumulate in the nucleus. But when 125I- or fluorescein isothiocyanate antibody FR-1 was co-introduced with HMG-1 into the cytoplasm of FL cells, it did migrate into the nucleus.

The scattering of electromagnetic waves from a perfectly conductive slightly random surface is studied by a probabilistic method developed recently. For a plane wave incident on a homogeneous, isotropic, Gaussian random surface, a stochastic wave solution involving multiple scattering effects is approximately obtained by use of the Wiener–Hermite expansion technique in the probability theory. Then the backscattering cross section per unit surface is derived for both like and cross polarization in a closed form and is shown in the figures. The surface waves propagating along the random surface are discussed.

Intracellular localization of nonspecific lipid transfer protein (nsLTP) in rat hepatocytes was investigated by immunoblot analysis of the subcellular fractions and immunoelectron microscopy, using affinity-purified antibody against nsLTP. Immunoblot analysis showed that the protein exists in the peroxisomal and cytosolic fractions. Further study indicated that nsLTP exists in the soluble subfraction of the peroxisomes. Immunoelectron microscopic observation revealed that nsLTP is highly concentrated in the matrices of the peroxisomes. From these results, we concluded that nsLTP mainly exists in the matrix of the peroxisomes. The role of nsLTP is discussed.

Performance testing of JT‐60 RF systems was completed in summer of 1986. In the integrated test of LHRF systems output power of eight klystrons was absorbed into water dummy loads at the level of 8 MW for 1 sec. at 2 GHz. In the ICRF case power test of each eight three‐stage amplifier was conducted at the level of 750 kW for 10 sec. at 120 MHz. In the current operation with JT‐60 plasma, each LHRF system has acheived 2.0–2.4 MW for seconds and the ICRF system has achieved 2.0 MW for 1 second.

The phased array launchers of 4×8 waveguide for current drive and heating in JT‐60 have been constructed and have operated at a power level of ∼2 MW for a few seconds. The transmitted power densities have reached 4.1 KW/cm2 and 2.1 KW/cm2 for current drive and heating launchers, respectively, after only a few weeks conditioning. The coupling efficiency of 80∼85% has been obtained at the power level of a few MW into 1∼2 MA plasma and the coupling efficiency is explained well with Brambilla’s theory.

FITC-labeled antibodies raised against chicken myofibrillar I-protein stained chicken myofibrils, which were fixed with formalin immediately after being cut from the sacrificed chicken breast muscle, at the junctional region of A-bands and I-bands. On the other hand, the antibodies stained the glycerinated myofibrils at the region around Z-bands. Aged glycerinated myofibrils stored in a cold room became stained with the same antibodies at the M-line and the A-band region except for the H-zone and the Z-band. I-Protein, which was originally localized at the A-I junctions, moved to the region around Z-bands and A-bands during the process of preparing myofibrils, paralleling the deterioration of myofibrils. Although I-protein is easily released from its original position, it is not a cytoplasmic protein of muscle but an intrinsic myofibrillar component, because immunoblotting tests showed that I-protein is contained in the myofibrillar fraction and not in the muscular cytoplasmic fraction.

The biosynthesis of nonspecific lipid transfer protein (nsLTP) was investigated. Total RNA of rat liver was translated in a rabbit reticulocyte lysate cell-free protein-synthesizing system with [35S]methionine as label. The immunoprecipitation of translation products with affinity-purified anti-nsLTP antibody yielded 14.5- and 60-kDa [35S]polypeptides. The molecular mass of the former polypeptide was approximately 1.5 kDa larger than that of the purified mature nsLTP (13 kDa). The site of synthesis of nsLTP was studied by in vitro translation of free and membrane-bound polyribosomal RNAs followed by immunoprecipitation. mRNA for both the 14.5- and 60-kDa polypeptides were found predominantly in the free polyribosomal fraction in both normal and clofibrate-treated rats. Clofibrate, a hypolipidemic drug that proliferates peroxisomes, did not increase the relative amount of nsLTP mRNA in rat liver. Pulse-chase experiments in rat hepatoma H-35 cells suggested that nsLTP was synthesized as a larger precursor of 14.5 kDa and converted to a mature form of 13 kDa. We have recently shown that nsLTP is highly concentrated in peroxisomes in rat hepatocytes [Tsuneoka et al. (1988) J. Biochem. 104, 560-564]. Taken together, these results suggest that nsLTP is synthesized as a larger precursor of 14.5 kDa on cytoplasmic free polyribosomes, then post-translationally transported to peroxisomes, where the precursor is presumably proteolytically processed to its mature form of 13 kDa. The relationship between the 13-kDa nsLTP and the 60-kDa polypeptide is also discussed.