A5089310771- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Graphite, nuclear technology, radiation studies
- Radiation Detection and Scintillator Technologies
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Nuclear and radioactivity studies
- Laser-Plasma Interactions and Diagnostics
- Radiation Therapy and Dosimetry
- Atomic and Subatomic Physics Research
- Ionosphere and magnetosphere dynamics
- Cold Fusion and Nuclear Reactions
- Plasma Diagnostics and Applications
- Radioactive contamination and transfer
- Particle Detector Development and Performance
- Medical Imaging Techniques and Applications
- Advanced X-ray and CT Imaging
- Nuclear Engineering Thermal-Hydraulics
- Reservoir Engineering and Simulation Methods
- Nuclear physics research studies
- Oil and Gas Production Techniques
- Radiation Shielding Materials Analysis
Culham Centre for Fusion Energy
2001-2024
National Transportation Research Center
2024
Oak Ridge National Laboratory
2024
Culham Science Centre
2001-2024
ITER
2013-2023
United Kingdom Atomic Energy Authority
2008
Joint European Torus
1990-1999
Princeton Plasma Physics Laboratory
1994-1995
Princeton University
1994-1995
Advanced Science Research Center
1994
High fusion power experiments using DT mixtures in ELM-free H mode and optimized shear regimes JET are reported. A of 16.1 MW has been produced an at 4.2 MA/3.6 T. The transient value the amplification factor was 0.95±0.17, consistent with high nDT(0)τEdiaTi(0) = 8.7 × 1020±20% m-3 s keV, maintained for about half energy confinement time until excessive edge pressure gradients resulted discharge termination by MHD instabilities. ratio DD to powers (from separate but otherwise similar...
Peak fusion power production of 6.2\ifmmode\pm\else\textpm\fi{}0.4 MW has been achieved in TFTR plasmas heated by deuterium and tritium neutral beams at a total 29.5 MW. These have an inferred central alpha particle density 1.2\ifmmode\times\else\texttimes\fi{}${10}^{17}$ ${\mathrm{m}}^{\mathrm{\ensuremath{-}}3}$ without the appearance either disruptive magnetohydrodynamics events or detectable changes Alfv\'en wave activity. The measured loss rate energetic particles agreed with...
After many years of fusion research, the conditions needed for a D–T reactor have been approached on Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. For first time unique phenomena present in plasma are now being studied laboratory plasma. The magnetic experiments to study plasmas using nearly equal concentrations deuterium and tritium carried out TFTR. At maximum power 10.7 MW, 39.5 MW neutral-beam heating, supershot discharge 6.7 high-βp following current rampdown....
The Tomamak Fusion Test reactor has performed initial high-power experiments with the plasma fueled nominally equal densities of deuterium and tritium. Compared to pure plasmas, energy stored in electron ions increased by \ensuremath{\sim}20%. These increases indicate improvements confinement associated use tritium possibly heating electrons \ensuremath{\alpha} particles created D-T fusion reactions.
A combination of recently installed state-of-the-art imaging and profile diagnostics, together with established plasma simulation codes, are providing for the first time on Mega Ampère Spherical Tokamak (MAST) tools required studying confinement transport, from core through to edge scrape-off-layer (SOL). The H-mode transport barrier is now routinely turned off using a poloidally localized fuelling fine balancing X-points. Theory, supported by experiment, indicates that radial electric field...
The principle needs of ITER with regard to nuclear analysis can be divided into the broad categories safety and licensing, plant operation, decommissioning although there is much overlap interdependence within these categories.This paper reviews status methods applied date recommends future strategy which should adopt address continuing requirements responsibilities. This done by consideration application radiation transport codes, creation an reference neutronics model, a results database,...
Abstract During ITER operational life, a remote-handled cask will be used to transfer In-Vessel components the Hot Cell for maintenance, storage and decommissioning purposes. Due distribution of penetrations system allocation in facility, radiation field each operation presents high spatial variability; all operations must studied independently workers electronics protection. In this paper, we present fully representative approach describe environment during complete remote-handling scenario...
During the JET Preliminary Tritium Experiment (PTE), an estimated 2 × 1012 (1.1 1021 atoms) of tritium were injected into vacuum vessel. A series experiments was performed whose purpose to deplete torus tritium, compare effectiveness different methods removal and obtain a quantitative understanding processes involved. The cleaning procedures such that normal tokamak programme resumed one week after PTE routing exhaust gases atmosphere two weeks. release from vessel found scale with deuterium...
Measurements from the JET neutron profile monitor are analyzed tomographically to deduce 2-D spatial distribution of emissivity during NBI heating both before and after sawtooth crashes. In a discharge where global emission decreases slightly 5/6 pre-crash rate nearly 1016 n s-1, axial drops much more only 1/6 value. The sources with an analytic Fokker-Planck formulation. main change in is due fast ion redistribution crash decrease beam-beam-produced emissivity. deduced consistent other...
The maximum temperature expected in ITER is the region of 40keV and minimum average density approximately 3×1019m−3 also expected. proven capability, convenience, port occupancy LIDAR Thomson scattering approach, demonstrated on JET, makes it an excellent candidate for ITER. Nonetheless, there are formidable design challenges realizing such a diagnostic system. high presents its own problem very large relativistic blueshift scattered spectrum (e.g., λ∕λ0∼0.35 Te=40keV), impacting laser...
The JET neutron emission profile monitor is used to measure the 2.5 MeV and 14 line integrals before after sawtooth crashes in high d-d yield, hot ion H mode plasmas Joint European Torus (JET). Deuterium-deuterium (d-d) fusion produces neutrons 1 tritons (t) at nearly equal rates from its two reaction channels. A plasma current of 3 MA sufficiently contain most product tritons, which have birth orbit gyroradii velocity space distributions similar those 3.5 or particles d-t fusion. By...
During the plasma pulses, neutron-induced activation of cooling water will produce an important contribution to radiation levels in ITER Tokamak Complex. The resulting field has a complex spatial distribution due combination decay and production radioisotopes intricate lines that feed numerous systems inside outside bio-shield. An accurate estimation is necessary ensure radiological zoning respected. As today, this issue been studied using simple, manually defined geometries with limited...
The ITER Tokamak Complex is the civil structure that will host and largest part of associated systems. dimensions are 120 m × 80 60 m, built mostly concrete, with over one thousand penetrations. During operation, a radiation field spread throughout complex from diverse sources. It must be characterized to check compliance limits for electronics allocation human intervention. However, production maps in task paramount sophistication due challenges adequately model MCNP sources involved. In...
During a series of experiments with tritium (T) in deuterium (D) plasmas the Joint European Torus (JET), temporal evolution and two dimensional (2-D) spatial profiles 2.5 14 MeV neutron emissivities from D-D D-T fusion reactions were inferred measurements JET emission profile monitor. These experiments, involving triton production fusion, beam deposition diffusion, removed wall tiles, investigated four plasma scenarios: (i) In high performance neutral injection, emissivity due to burnup was...