(Critical topics of plasma facing materials/plasma facing component data for the next step fusion devices)
The Unites States-Japan Workshop P-165 brought together approximately 60 scientists and engineers to discuss critical topics of plasma facing materials and components for the next-step fusion device. In addition to the United States and Japanese participants, there were several guest attendees from Europe. The international makeup of the participants greatly enhanced the success of the workshop. The author jointly chaired a workshop session entitled Impact of Neutron Effects to Plasma Facing Materials and Plasma Facing Component (PFC) Feasibilities for the International Thermonuclear Experimental Reactor (ITER),'' and presented an overview paper on neutron effects and materials selection for the next-step plasma facing devices. The author presented his work on the effects of neutron irradiation on graphites and carbon-carbon (c/c) composite materials, which are strong candidate materials for PFC's in ITER. The workshop addressed many issues of current concern to the PFC/PFM community including: plasma erosion of PFM's; trapping/detrapping of hydrogen isotopes; large machine operating experience; and extent of the materials database.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6307963
- Report Number(s):
- ORNL/FTR-3853; ON: DE91005987
- Country of Publication:
- United States
- Language:
- English
Similar Records
Performance of Plasma-Facing Materials Under Intense Thermal Loads in Tokamaks and Stellarators
Tritium behavior in eroded dust and debris of plasma-facing materials.
US -- Japan workshops: Q-111, Development of plasma facing components and materials for next large fusion devices, and Q-112, Vacuum and first wall technology for fusion devices
Journal Article
·
Thu Jul 15 00:00:00 EDT 2004
· Fusion Science and Technology
·
OSTI ID:20849729
Tritium behavior in eroded dust and debris of plasma-facing materials.
Conference
·
Mon Mar 09 23:00:00 EST 1998
·
OSTI ID:10681
US -- Japan workshops: Q-111, Development of plasma facing components and materials for next large fusion devices, and Q-112, Vacuum and first wall technology for fusion devices
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6242556
Related Subjects
36 MATERIALS SCIENCE
360605 -- Materials-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ASIA
CARBON
CLOSED PLASMA DEVICES
DAMAGING NEUTRON FLUENCE
ELEMENTAL MINERALS
ELEMENTS
FIRST WALL
GRAPHITE
JAPAN
MATERIALS
MEETINGS
MINERALS
NEUTRON FLUENCE
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
TRAVEL
360605 -- Materials-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ASIA
CARBON
CLOSED PLASMA DEVICES
DAMAGING NEUTRON FLUENCE
ELEMENTAL MINERALS
ELEMENTS
FIRST WALL
GRAPHITE
JAPAN
MATERIALS
MEETINGS
MINERALS
NEUTRON FLUENCE
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
TRAVEL