Design of a tokamak fusion reactor first wall armor against neutral beam impingement

Technical Report · Thu Dec 01 04:00:00 EST 1977

DOI:https://doi.org/10.2172/6439778· OSTI ID:6439778

Myers, R A

The maximum temperatures and thermal stresses are calculated for various first wall design proposals, using both analytical solutions and the TRUMP and SAP IV Computer Codes. Beam parameters, such as pulse time, cycle time, and beam power, are varied. It is found that uncooled plates should be adequate for near-term devices, while cooled protection will be necessary for fusion power reactors. Graphite and tungsten are selected for analysis because of their desirable characteristics. Graphite allows for higher heat fluxes compared to tungsten for similar pulse times. Anticipated erosion (due to surface effects) and plasma impurity fraction are estimated. Neutron irradiation damage is also discussed. Neutron irradiation damage (rather than erosion, fatigue, or creep) is estimated to be the lifetime-limiting factor on the lifetime of the component in fusion power reactors. It is found that the use of tungsten in fusion power reactors, when directly exposed to the plasma, will cause serious plasma impurity problems; graphite should not present such an impurity problem.

• Research Organization: California Univ., Berkeley (USA). Lawrence Berkeley Lab.
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6439778
• Report Number(s): LBL-8254
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BEAM INJECTION
CARBON
DESIGN
ELEMENTS
FIRST WALL
GRAPHITE
IMPURITIES
METALS
NEUTRAL ATOM BEAM INJECTION
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REFRACTORY METALS
SHIELDING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
TUNGSTEN