Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Pulsed-field heating in tokamak reactor TF-coil helium vessels

Conference ·
OSTI ID:5968600
Pulsed field heating in superconduting TF-coil helium vessels in tokamak reactors such as INTOR, ETF, STARFIRE and FED has been studied. One design feature common to these reactors is that most of the high current poloidal coils are placed outside of the TF-coil envelope. As a result, some of the poloidal coils will require very large currents (> 10 MA) for plasma stabilization. For the case of INTOR, this fact is aggravated by the requirement of having divertor coils in the poloidal coil system, which may require up to 28 MA in a single coil, with local poloidal fields of up to 5 T being generated at the TF-coil. During plasma startup and shutdown, the ramping of currents in these poloidal coils will generate large eddy current heating in the TF-coil helium vessels which are constructed with stainless steel. Furthermore, during plasma disruption, the rapid field change will also generate excessive heating in the helium vessels. Analyses have been made on the heat loads introduced by such eddy current heating, and the impacts on the reactor design are discussed. Schemes for alleviating the problems are also discussed.
Research Organization:
General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
AT03-76ET51011
OSTI ID:
5968600
Report Number(s):
GA-A-16510; CONF-811040-98; ON: DE82003205
Country of Publication:
United States
Language:
English