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Additionally to having an API key associated with your account, exporting private event information requires the usage of a persistent signature. This enables API URLs which do not expire after a few minutes so while the setting is active, anyone in possession of the link provided can access the information. Due to this, it is extremely important that you keep these links private and for your use only. If you think someone else may have acquired access to a link using this key in the future, you must immediately create a new key pair on the 'My Profile' page under the 'HTTP API' and update the iCalendar links afterwards. A full-scale ITER toroidal interferometer and polarimeter (TIP) prototype has been constructed and tested both in the laboratory and on the DIII-D tokamak.
The TIP prototype measures electron density using two approaches. Two-color interferometry is carried out at 10.59μm and 5.22μm using a CO2 and Quantum Cascade Laser (QCL) respectively while a separate polarimetry measurement of the plasma induced Faraday effect, is made at 10.59μm. High-resolution TIP phase information is obtained using an FPGA based phase demodulator and precision clock source. The TIP is also equipped with a piezo tip/tilt stage active feedback alignment system which minimizes noise and maintains diagnostic alignment indefinitely. A 120 m path length laboratory prototype was used to test components and demonstrate alignment techniques, feedback alignment capabilities, and determine diagnostic noise floors.
Phase errors of 1.5 degrees for the interferometer and 0.06 degrees for the polarimeter have been demonstrated for 1000 seconds. The system is now operational on the DIII-D tokamak, using a geometry and path length similar to ITER, and has successfully demonstrated the ITER requirements for both interferometry and polarimetry. Work supported by U.S. DOE Contracts DE-AC-02-09CH11466 and DE-FC02-04ER54. A novel optical spectrometer was built that enables measurements of Thomson scattering from electron plasma waves with 2-ps time resolution. Pulse-front tilt introduced from a diffraction grating scales with aperture diameter and can limit the achievable time resolution of a streaked spectrometer. The spectrometer presented in this work uses an echelon optic to break the aperture into series of temporally delayed segments that compensate for the large-scale optical path length asymmetry introduced by the grating.
By decoupling the relationship between pulse-front tilt and aperture size, an optimized spectrometer design can be matched to the time resolution of the streak camera at an arbitrarily large throughput. The as-built streaked spectrometer operates with an effective aperture of f/3.3 with 1-nm spectral resolution covering a range of 460 nm to 590 nm and records spectra with 2-ps time resolution. The system has been implemented to study plasma heating rates of underdense plasmas by observing Thomson scattering from electron plasma waves. This material is based upon work supported by the Department of Energy National Nuclear Security Administration under Award Number DE-NA0001944. A digital holography (DH) surface erosion/deposition diagnostic is being developed for 3D imaging of plasma facing component (PFC) surfaces in situ and in real time. Digital holography is a technique that utilizes lasers reflected from a material surface to form an interferogram, which carries information about the topology of the surface when reconstructed.
As described in this paper, dual CO2 lasers at 9.271 and 9.250 microns illuminate the interrogated surface (at a distance of 1 m) in a region of 1 cm x 1 cm. The surface feature resolution is 0.1 mm in the plane of the surface, and the depth resolution ranges from 0.001 to 2 mm perpendicular to the surface. The depth resolution lower limit is set by single-laser and detector optical limitations, while the upper limit is determined by 2 pi phase ambiguity of the dual-laser synthetic wavelength. Measurements have been made “on the bench” to characterize the single-laser and dual-laser DH configurations utilizing standard resolution targets and material targets that were previously exposed to high flux plasmas either in the Prototype Material Plasma Exposure eXperiment (Proto-MPEX) or electro-thermal (ET) arc source.
Typical DH measurements were made with 0.03 ms integration with an IR camera that can be framed at rates approaching 1.5 kHz. The DH diagnostic system is progressing towards in situ measurements of plasma erosion/deposition either on Proto-MPEX or the ET arc source. The Magnetic Recoil neutron Spectrometer (MRS) at the OMEGA laser facility has been routinely used to measure deuterium-tritium (DT) yield and areal density in cryogenically layered implosions since 2008. Recently, operation of the OMEGA MRS in higher-resolution mode with a smaller, thinner (4 cm2, 57-um thick) CD conversion foil has also enabled inference of the apparent DT ion temperature (Tion) from MRS data. Tion inferred from the broadening of the MRS-measured primary DT neutron spectrum compares well with neutron time-of-flight-measured Tion.
This result is important as it demonstrates good understanding of the different systematics associated with the two independent measurements. The MRS resolution in this configuration (sigma=0.37 MeV) is still higher than required for a high-precision Tion measurement.
In this contribution, we also discuss paths forward for further improving the resolution of the OMEGA MRS, including fielding a smaller foil closer to target chamber center. This work was supported in part by the U.S. Department of Energy and by the Laboratory of Laser Energetics under Contract 415935-G.
Metallic first mirrors will be components for optical spectroscopy and imaging systems in ITER. A comprehensive First Mirror Test (FMT) was carried out in JET with the ITER-Like Wall (ILW): over 60 Mo mirrors facing plasma in the main chamber and in divertor during three ILW campaigns (up to 62 h total). Reflectivity measurements (300-2400 nm) and surface characterization with electron and ion spectroscopy were done before and after exposure. Total reflectivity of mirrors from the main chamber wall is decreased by 2-3% from the initial value.
Surfaces are coated by a thin co-deposit (5-15 nm) containing D, Be, C and O. This affected the optically active layer (15-20 nm on Mo) thus leading to the increase of diffuse reflectivity by a factor of 1-2.
All mirrors from the divertor (inner, outer, base) lost reflectivity by 20-80%. This result confirms earlier findings, but there are significant differences in the surface state dependent on the mirror location and exposure time, i.e.
Either single or all three ILW campaigns. This is caused by beryllium-rich deposits. The thickest layers are in the outer divertor: 850 nm. Other elements also are in deposits on all divertor mirrors: O, C, W, and Ni. The comparison between results from JET with carbon and metal wall will be presented. The behavior of 1 MeV triton has been studied in order to understand alpha particle confinement property in toroidal devices.
Time-resolved triton burnup study has been performed by scintillating fiber detectors (Sci-Fi) in large tokamaks 1 and helical systems 2. The time-integrated triton burnup ratio was successfully measured by activation foils technique in medium sized tokamak 3, 4. To obtain time evolution of 14 MeV neutron rate under the neutron emission rate of 10^13 n/s to 10^14 n/s in KSTAR, we designed high detection efficiency Sci-Fi having a diameter (f) of 160 mm. In the head of detector1, 2000 scintillating fibers having f of 1 mm and length of 50 mm are embedded, whereas 1000 scintillating fibers having f of 2 mm and length of 50 mm are embedded in the head of detector2. The detection efficiency of those detectors is expected to be one order higher than the detectors used in large tokamaks 1.
Experimental results performed using an accelerator-based neutron generator in Fast Neutron Laboratory and OKTAVIAN will be reported.1 Barnes C. Et al 1998 Nucl. Fusion 38 597.2 K.
Ogawa et al., submitted to Nuclear Fusion.3 J. Et al 2016 Rev. 87 11D828.4 M. Hoek et al., IPP-Report IPP 1/320 March 1999. We report tests of an alternate technique for constraining MHD equilibrium analysis in tokamak plasmas using internal magnetic field measurements based on B measurements from motional Stark splitting of Dα spectral lines emitted by a neutral heating beam (MSE-LS). We compare results using MSE-LS with those of the standard equilibrium analysis technique based on line polarization of the Dα emission (MSE-LP).
An alternative to MSE-LP is needed in future devices such as ITER where MSE-LP will be difficult due to plasma-induced coating of the first optical element. The tests utilized data from 10 DIII-D shots with 7 MSE-LS and 14 MSE-LP views covering a range of radii along the outer midplane of the plasma.
Seven MSE-LS measurements can contribute significantly to equilibrium reconstruction of pressure and q profiles using both synthetic and experimental DIII-D MSE-LS data. For example, 7 MSE-LS plus seven MSE-LP measurements give a fit quality that is as good as the same cases with 14 MSE-LP measurements. Analyzing synthetic data for 14 MSE-LS measurements shows significant improvement in fitting quality over the case with 7 MSE-LS locations. This work supported by DoE DE-FC02-04ER54698 and DE-AC02-09CH11466. Inertial confinement fusion self-emission imaging provides a challenging environment for two-dimensional time resolved x-ray imaging. The short lived (200 ps) spherical implosion dynamically evolves throughout the deuterium-tritium (DT) compression.
Current microscopes with 10 µm spatial resolution and 20-100 ps time resolution provide sufficient information to infer hot spot volume and emissivity under certain physical constraints. The introduction of high-atomic number materials as shell dopants, in conjunction with the susceptibility of the implosion to seeded hydrodynamic growth, has led to continued observations of high-spatial-frequency x-ray bright spots that evolve internally to the hot DT core. We wish to determine the origin and nature of these features through the application of higher resolution x-ray microscopes. This goal requires addressing both the image forming system and the detector resolution and statistics, in addition to the physics we hope to infer. With new reflective x-ray optics and coded aperture imaging being considered alongside the next generation of fast x-ray detectors, this paper addresses the instrument design requirement to measure ‘bright spot’ features at the NIF. Prepared by LLNL under Contract DE-AC52-07NA27344. Thomson scattering (TS) system is one of the useful diagnostics to measure electron temperature and density in fusion plasmas.
The multi-pass Thomson scattering (MPTS) system is useful technique for increasing the TS signal intensities and improving the TS diagnostic time resolution. The MPTS system developed in GAMMA 10/PDX has a polarization-based configuration with an image relaying system. The MPTS system has been constructed for enhancing the Thomson scattered signals for the improvement of measurement accuracy and the MHz sampling time resolution. However, in the normal MPTS system, the MPTS signal intensities decrease with the pass number, because of the damping due to the constructed optical components. Then we have been developing the new MPTS system with the laser amplification system. The laser amplification system can improve the degraded laser power after six passed in the multi-pass system to the initial laser power.
We successfully obtained the continued multi-pass signals after the laser amplification system in the gas scattering experiments for the first time. Charge exchange spectra from the interaction of fully ionized Carbon impurity ions and injected neutral beam on EAST have been utilized to provide the plasma ion temperature and rotation velocity since the cCXRS was installed on EAST at 2014. However, the concentration of carbon became especially low on EAST with the tungsten divertor in the latest experimental campaign, it is necessary to investigate the CX lines from the other impurity ions. The cCXRS system was enhanced recently to extend its wavelength coverage and preserve the spatial channels at the same time. A pixel, back-illuminated frame-transfer CCD camera with on-chip multiplication gain was used. The bandpass filter centered on 529.1nm was removed and one entrance slit was used to enable a wide spectral band at one acquisition, and the emission lines of CVI at 529.1 nm, of NeX at 524.9 nm, and of LiIII at 516.7 nm could be observed simultaneously. The system contains 29 channels, and one channel is used for the real-time wavelength calibration.
The simultaneous measurement of CVI, NeX, and LiIII lines was performed by puffing neon gas and dropping lithium power at the same time during the 2016 EAST experimental campaign. In the paper, the experimental hardware is described and preliminary measurements will be shown. Self-sustaining fusion plasmas must be maintained by the power transfer from fusion born alpha particles to the thermal plasmas during slowing down process. Thus, the confinement of energetic alpha particles is crucial for a thermonuclear reactor in the future. The fast ions are primarily generated by applying auxiliary heating systems such as neutral beam injection and ion cyclotron resonance heating in current experiments.
The information of the fast ions can be accessed by different fast-ion diagnostic systems. The velocity-space sensitivities of fast-ion diagnostics are given by so-called weight functions. The Time-Of-Flight Enhanced Diagnostics (TOFED) neutron spectrometer has been installed at EAST tokamak to perform advanced neutron emission spectroscopy (NES) diagnosis of deuterium plasmas. Here, instrument-specific weight functions of TOFED were presented by taking the instrumental response into account.
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The velocity-space sensitivity of a measured time-of-flight spectrum from TOFED can be directly determined by the calculated weight functions. While xenon is the standard propellant for a wide range of plasma thrusters, xenon is expensive and xenon propellant systems require heavy compressed gas tanks, pressure regulators, and other bulky hardware. Iodine has similar mass and is much easier to acquire than xenon. Iodine’s natural state of matter at room temperature is solid and is easily sublimated to gas with a simple heating element.
This advantage for iodine is also a significant challenge when developing gas handling systems for iodine. Another challenge for iodine thrusters is a lack of well-defined spectroscopic diagnostics for single ionized iodine, specifically, a lack of a demonstrated laser induced fluorescence (LIF) scheme.
We present emission spectroscopy measurements of iodine ion emission from the 6p^5P3-5d^5 D4^o transition at 695.868 nm and the 6p^5P3-6s^5S2^o transition at 516.12 nm as a function of microwave power for a microwave excited iodine plasma in a sealed quartz cell at a pressure of 1 mTorr. The 5d^5D4^o state is metastable and was identified by Hargus et al. 48th AIAA Joint Propulsion, 2012 as a strong candidate for an iodine ion LIF scheme. We will also present preliminary LIF measurements using this three-level scheme with a tunable dye laser operating at 695.878 nm.
Streaked Thomson scattering measurements have been performed on plasma jets created from a 15 µm thick radial Al, Ti, or Cu foil load on COBRA, a 1 MA pulsed power machine. The streaked system enables collecting scattered light from two separate laser pulses separated in time by between 3 and 14 ns. This time difference is created by splitting the initial 3 ns duration, 10 J, 526.5 nm laser beam into two separate pulses, each with 2.5 J. Both energy laser pulses are shown to heat the plasma jet by inverse bremsstrahlung radiation, as measured by the streaked Thomson scattering system.
Analysis of the streak camera image showed that the electron temperature of the Al jet was increased from 20 eV up to 50 eV within about 2 ns for both laser pulses. The Ti and Cu jets both showed heating as well as sharp and complicated ion-acoustic features that were not apparent in the Al jet. Results will be presented from imaging two different fibers that viewed the plasma jet from two different scattering angles on the streak camera entrance slit simultaneously to compare temperature measurements and have a measure of the plasma density Froula et al. PRL 2005.This research is supported by the NNSA Stewardship Sciences Academic Programs under DOE Cooperative Agreement DE-NA0001836.
A pulse dilation photo-multiplier tube (PD-PMT) is a newly developed capability, which improves on the temporal resolution of conventional PMTs by approximately an order of magnitude. The corresponding gains in detail of inertial confinement fusion burn histories (10's of picoseconds wide in experiments in the National Ignition Facility), could be used to distinguish overlapping burn histories of different reactants.A PD-PMT uses a decreasing voltage ramp to apply a time varying e-field acceleration to electrons generated by a photocathode to stretch the signal in time (dilate). As earlier electrons are accelerated more than later electrons, the signal is dilated to improve resolution in a short (ns) time window.
A production PD-PMT was characterised at the Orion laser using the Optical Pulse Generator of the short pulse lasers. The PD-PMT was tested by varying operating parameters, input laser pulses, separations of a laser input pulses, and the position of the input laser pulses relative to the start of the ramped voltage (dilation window scan). As well varying the input intensity to quantify the linearity, and translating an apertured beam across the photocathode to assess the spatial uniformity. This poster will outline the characterised performance of the PD-PMT. We have developed a Wolter x-ray imager on the Z Machine to study the emission of warm x-ray sources with x-ray energies above 15 keV. As x-ray energy increases, imaging these sources with both high resolution and signal-to-noise becomes increasingly difficult using existing pinhole camera techniques. A Wolter optic has been adapted from observational astronomy and medical imaging for Z and uses curved x-ray mirrors to form a 2D image of a source with 5x5x5mm FOV and measured 180-μm resolution on-axis.
The mirrors consist of a multilayer that is tuned to allow x-rays within a narrow energy band to be collected by the optic. This multilayer, along with the larger collection solid angle makes the Wolter optic much more efficient at imaging x-rays compared to a traditional pinhole camera. Here we present the experimental design and implementation of the Wolter x-ray imager on Z, which is initially optimized to view Mo K-alpha x-rays (17.5 keV). In addition, we present a brief overview of its measured imaging performance and considerations for image deblurring.
Speakers: Jeffrey R. Fein ( Sandia National Laboratories), David Ampleford ( Sandia National Laboratories), Julia K.
Vogel ( Lawrence Livermore National Laboratory), Bernie Kozioziemski ( Lawrence Livermore National Laboratory), Chris Walton ( Lawrence Livermore National Laboratory), Ming Wu ( Sandia National Laboratories), Andrew Ames ( Harvard Smithsonian Center for Astrophysics), Jay Ayers ( Lawrence Livermore National Laboratory), Christopher R. Optical Thomson scattering (OTS) can be used to provide temporally and spectrally-resolved information on under-dense, high temperature plasmas. Scattering from the high-frequency collective excitations of the electrons can be used to constrain the temperature and number density of the electrons based on the width, amplitude and location of resonances in the scattered spectrum. The ion acoustic spectral features provide estimates of the ion and electron temperature ratio as well as the plasma mean ionisation state. These spectra can be streaked allowing the time evolution of the plasma conditions to be studied. In this presentation we discuss the development of an OTS diagnostic for the Orion laser system at AWE, UK. A 3ω probe beam will be used and the light scattered by the volume of plasma under study will be collected using a reflective telescope system.
Light from the ion and electron features can be split into two spectrometers, one covering the narrow bandwidth of the acoustic waves with high resolution and a second spectrometer to cover the broader wavelength range of the plasma waves. Time resolved data can then be obtained by relaying the spectrally resolved signal onto an optical streak camera. © British Crown Owned Copyright 2018/AWE. Several compact neutron spectrometers are now installed at EAST to obtain the information of fuel ions produced in core plasmas. Here, a stilbene and an NE213 liquid scintillator neutron spectrometers will be discussed.
Both of the spectrometers have a horizontal line of sight, while at different positions, and are proved to show good performance when the NBI auxiliary heating system is applied. Taking the response function into consideration, the velocity-space sensitivities given by the instrument-specific weight function of the beam-thermal part of neutron energy spectra in D-D plasma are derived for both the spectrometers. This method is supposed to make it possible to directly determine the contribution from a given velocity-space distribution of the fast ions to the measurement results. The one-dimensional imager of neutrons (ODIN) at the Sandia Z facility consists of a 10-cm block of tungsten with rolled edges, creating a slit imager width of either 250, 500, or 750 µm. Designed with a 1-m neutron imaging line of sight, we achieve about 4:1 magnification and 500-µm axial spatial resolution. The baseline ICF concept at Sandia is magnetized liner inertial fusion (MagLIF), which nominally creates a 1-cm line source of neutrons.
ODIN was designed to determine the size, shape, and location of the neutron producing region, furthering the understanding of compression quality along the cylindrical axis of magnetized liner implosions. Challenges include discriminating neutron images from hard x-rays and gammas with adequate signal-to-noise in the 2e12 DD neutron yield range, as well as understanding the neutron response function through the imager to various imaging detectors (namely CR-39). Modeling efforts were conducted with MCNP6.1 to determine neutron response functions for varying configurations in a clean DD neutron environment (without x-rays or gammas). Configuration alterations that will be shown include rolled-edge slit orientation and slit width, affecting resolution and response function.Work supported by DOE NNSA contract DE-NA0003525. Speakers: Jeremy Vaughan ( University of New Mexico), Carlos Ruiz ( Sandia National Laboratories), David Fittinghoff ( 2Lawrence Livermore National Laboratory), Mark May ( 2Lawrence Livermore National Laboratory), David Ampleford ( 1Sandia National Laboratories), Gary Cooper ( University of New Mexico), Gordon Chandler ( 1Sandia National Laboratories), Kelly Hahn ( 1Sandia National Laboratories), Perry Alberto ( 1Sandia National Laboratories), Jose Torres ( 1Sandia National Laboratories), Brent Jones ( 1Sandia National Laboratories).