Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
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Các bài báo tiêu biểu
Thermal response and thermal-hydraulic analysis of PFC baking for SST-1 tokamak
- Trang 469-472
Steady state Superconducting Tokamak (SST-1) to address some of the physics and
technology issues related to steady state tokamak operation. The plasma facing
components (PFC) of SST-1, placed inside the vacuum vessel (VV) of the tokamak,
are designed to be compatible for steady state operation. The main consideration
in the design of the PFC is the steady state heat removal of up to 1 MW/m/sup
2/...
#Tokamaks #Steady-state #Plasma temperature #High temperature superconductors #Superconducting coils #Nitrogen #Thermal loading #Impurities #Heat transfer #Physics
Nghiên cứu và thiết kế thủy nhiệt của các thành phần tiếp xúc plasma (PFC) làm mát bằng nước cho tokamak SST-1 Dịch bởi AI
- Trang 422-425
Các thành phần tiếp xúc plasma (PFC) là một phần quan trọng trong thiết kế của
Tokamak Siêu dẫn Chế độ Bền (SST-1). PFC của SST-1 bao gồm các thiết bị rẽ dòng,
các thiết bị ổn định thụ động, các vách ngăn và các giới hạn, được thiết kế để
tương thích với hoạt động chế độ bền. Điều quan trọng nhất trong thiết kế PFC là
khả năng tản nhiệt ổn định lên tới 1 MW/m/sup 2/. Trong quá trình vận hành ổn
đị...
#Tokamaks #Steady-state #Tiles #Cooling #Surface fitting #Temperature distribution #Thermal loading #Coolants #Plasma temperature #Finite difference methods
Structural design and analysis for the KSTAR cryostat
- Trang 396-399
The KSTAR cryostat is a 8.8 m diameter vacuum vessel that provides the necessary
thermal barrier between the ambient temperature test cell and the supercritical
helium cooled superconducting magnet providing the base pressure of 1/spl
times/10/sup -5/ torr. The cryostat is a single walled vessel consisting of
central cylindrical section and two end closures, a flat base structure with
external rei...
#Magnetic analysis #Superconducting magnets #Plasma temperature #Testing #Helium #Leg #Concrete #Bellows #Thermal loading #Performance analysis
Compact probe design for power monitoring from the narrow side of the reduced height waveguide
- Trang 268-271
Due to confined space in a stack of reduced height waveguides, power detection
of the incident and reflected wave in the reduced height waveguide is extremely
difficult. A new compact probe to monitor the incident and reflected wave from
the narrow side of the reduced height waveguide has been developed. This compact
probe consists of 2 current loops, a directional coupler, and a small trimmer
cap...
#Probes #Monitoring #Directional couplers #Impedance #Power transmission lines #Plasma confinement #Capacitors #Testing #Tokamaks #Power cables
The National Ignition Facility: status and plans for laser fusion and high-energy-density experimental studies
- Trang 487-492
The National Ignition Facility (NIF), currently under construction at the
University of California's Lawrence Livermore National Laboratory is a $2.25B
stadium-sized facility containing a 192-beam, 1.8-Megajoule, 500-Terawatt,
351-nm laser system. NIF is being built by the National Nuclear Security Agency
and when completed will be the world's largest laser system, providing a
national center to s...
#Ignition #Laser fusion #Laser theory #Laboratories #National security #Inertial confinement #Physics #Laser beams #Structural beams #Temperature
Status of the Experimental Physics and Industrial Control System at NSTX
- Trang 245-247
The NSTX achieved first plasma in 1999. The Experimental Physics and Industrial
Control System (EPICS) is used to provide data-integration services for
monitoring and control of all NSTX engineering subsystems. EPICS is a set of
software initially developed at US DOE laboratories. It Is currently used and
maintained through a global collaboration of hundreds of scientists and
engineers. This paper...
#Physics #Industrial control #Maintenance engineering #Reliability engineering #Software tools #Plasma applications #Monitoring #Control systems #Data engineering #US Department of Energy
Industrial hygiene concerns during the decontamination and decommissioning of the Tokamak Fusion Test Reactor
- Trang 111-113
A significant industrial hygiene concern during the decontamination and
decommissioning (D&D) of the Tokamak Fusion Test Reactor (TFTR) was the
oxidation of the lead bricks' surface, which were utilized for radiation
shielding. This presented both airborne exposure and surface contamination
issues for the workers in the field removing this material. This paper will
detail the various protection an...
#Decontamination #Tokamaks #Testing #Lead #Occupational safety #Surface contamination #Blood #Bones #Inductors #Laboratories
Upgraded alignment control for the DIII-D Thomson scattering laser system
- Trang 180-183
The Thomson scattering system measures electron density and temperature with the
aid of eight pulsed Nd:YAG lasers on the DIII-D tokamak. DIII-D is the United
States National Fusion Facility for magnetic confinement fusion experiments. The
Thomson system probes the tokamak in three separate regions. The measurements
from the different regions produce density and temperature profiles during
plasma ...
#Optical control #Control systems #Plasma temperature #Automatic control #Optical scattering #Laser fusion #Plasma measurements #Laser beams #Light scattering #Density measurement
Results from the MAST spherical tokamak
- Trang 454-460
The MAST (Mega-Amp Spherical Tokamak) experiment has been operational since Jan
2000. Results from MAST are important both in evaluating the potential of future
ST fusion devices, and in developing understanding of processes relevant to
conventional aspect ratio tokamaks. In this paper methods of initiating, ramping
up, and sustaining the high plasma currents associated with ST fusion devices
are ...
#Tokamaks #Heating #Physics #Solenoids #Educational institutions #Plasma devices #Plasma diagnostics #Particle beams #Plasma applications #Plasma density
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
- 2002
Presents the front cover of the proceedings record.