Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.015 seconds
Onega, R.J.; Becraft, W.R.; Bettis, E.S.
Oak Ridge National Lab., TN (USA)1979
Oak Ridge National Lab., TN (USA)1979
AbstractAbstract
[en] Evaluation of the instrumentation and control of a power producing tokamak fusion reactor such as The Next Step (TNS) requires an assessment of the consequences of a major plasma disruption during reactor operation. The most important consequence of a disruption will be damage to the first wall from thermal and magnetic stress. Severe temperature gradients will cause thermal stress, placing a limit on the number of disruptions that can occur before the integrity of the wall is lost, and eddy currents induced in the wall will interact with the magnetic energy of the plasma and the →B/sub T/ field to create mechanical forces. Consequences to the ohmic heating (OH) coils, their power supplies, and other coils must also be taken into account
Primary Subject
Source
Feb 1979; 60 p; Available from NTIS., PC A04/MF A01
Record Type
Report
Literature Type
Numerical Data
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue