Neutron transport and activation analysis for the IGNITEX device

Conference · Wed Mar 01 04:00:00 EST 1989 · Fusion Technol.; (United States)

OSTI ID:6217392

Parish, T A; Carrera, R; Hertel, N E; Montalvo, E

IGNITEX is a tokamak experimental device that is designed to study alpha particle heating and ignition in D-T plasmas. To make possible a small, simple, and low cost experiment, IGNITEX will employ Ohmic heating to reach ignition and very high magnetic fields from an unconventional single turn toroidal field coil. As the initial step in the safety analysis for IGNITEX, radiation transport through the device and its surrounding concrete shield has been calculated using ANISN. Activation of the IGNITEX structure was computed using REAC2. The inventory of radioactive material produced by operation of IGNITEX is not expected to present any significant waste disposal or ventilation problems.

• Research Organization: Texas A and M Univ., Nuclear Engineering Dept., TX (US); Center for Fusion Engineering, Univ. of Texas at Austin, TX (US)
• OSTI ID: 6217392
• Report Number(s): CONF-881031-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
• Country of Publication: United States
• Language: English

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A CODES
ACTIVATION ANALYSIS
ALPHA PARTICLES
BUILDING MATERIALS
CHARGED PARTICLES
CHEMICAL ANALYSIS
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COMPUTER CALCULATIONS
COMPUTER CODES
CONCRETES
D-T REACTORS
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
EXPERIMENTAL REACTORS
HEATING
I CODES
MAGNET COILS
MAGNETIC FIELDS
MANAGEMENT
MATERIALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PINCH DEVICES
PLASMA HEATING
R CODES
RADIATION TRANSPORT
RADIOACTIVE WASTE DISPOSAL
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SHIELDS
STEADY-STATE D-T REACTORS
STEADY-STATE FUSION REACTORS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
TOROIDAL PINCH DEVICES
VENTILATION
WASTE DISPOSAL
WASTE MANAGEMENT