Transport simulations of ohmic ignition experiment: IGNITEX

Conference · Tue Dec 01 00:00:00 EST 1987

OSTI ID:5510031

Uckan, N. A.; Howe, H. C.

The IGNITEX device, proposed by Rosenbluth et al., is a compact, super-high-field, high-current, copper-coil tokamak envisioned to reach ignition with ohmic (OH) heating alone. Several simulations of IGNITEX were made with a 0-D global model and with the 1-D PROCTR transport code. It is shown that OH ignition is a sensitive function of the assumptions about density profile, wall reflectivity of synchrotron radiation, impurity radiation, plasma edge conditions, and additional anomalous losses. In IGNITEX, OH ignition is accessible with nearly all scalings based on favorable OH confinement (such as neo-Alcator). Also, OH ignition appears to be accessible for most (not all) L-mode scalings (such as Kaye-Goldston), provided that the density profile is not too broad (parabolic or more peaked profiles are needed), Z/sub eff/ is not too large, and anomalous radiation and alpha losses and/or other enhanced transport losses (eta/sub i/ modes, edge convective energy losses, etc.) are not present. In IGNITEX, because the figure-of-merit parameters are large, ignition can be accessed (either with OH heating alone or with the aid of a small amount of auxiliary power) at relatively low beta, far from stability limits. Once the plasma is ignited, thermal runaway is prevented naturally by a combination of increased synchrotron radiation, burnout of the fuel in the plasma core and replacement by thermal alphas, and the reduction in the thermal plasma confinement assumed in L-mode-like scalings. 12 refs., 5 figs., 1 tab.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5510031
• Report Number(s): ORNL/TM-10617; CONF-871007-88; ON: DE88006055
• Resource Relation: Conference: 12. symposium on fusion engineering, Monterey, CA, USA, 12 Oct 1987; Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TOKAMAK DEVICES
THERMONUCLEAR IGNITION
COMPUTERIZED SIMULATION
GLOBAL ANALYSIS
JOULE HEATING
PLASMA CONFINEMENT
PLASMA SCRAPE-OFF LAYER
POWER LOSSES
SCALING LAWS
SYNCHROTRON RADIATION
TRANSPORT THEORY
BOUNDARY LAYERS
BREMSSTRAHLUNG
CLOSED PLASMA DEVICES
CONFINEMENT
ELECTRIC HEATING
ELECTROMAGNETIC RADIATION
ENERGY LOSSES
HEATING
LAYERS
LOSSES
MATHEMATICS
PLASMA HEATING
RADIATIONS
RESISTANCE HEATING
SIMULATION
THERMONUCLEAR DEVICES
700101* - Fusion Energy- Plasma Research- Confinement
Heating
& Production