First wall and vacuum vessel analysis for Compact Ignition Tokamaks
- 1. TRW Inc., One Space Park, Redondo Beach, CA 90278
Description
This paper describes the ongoing analysis efforts supporting the design of the first wall (FW) and vacuum vessel (VV) components for the Compact Ignition Tokamak (CIT). Thermal and stress analyses of FW graphite tiles have established a nominal tile thickness of 1.0 cm and a maximum allowable FW surface heat flux of 11.0 MW/m/sup 2/. Calculations have shown that for a cooldown time of one hour, the required tile to VV thermal conductance is > 0.1 W/K. Estimates of worst-case electromagnetic loads and resulting stresses on the VV during plasma disruptions have shown the maximum stress levels to be below the allowable limits for the VV material. These results demonstrate that the selected FW/VV concept is consistent with the design objectives
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 10
- Journal Issue
- 3
- Series
- Fusion Technol.
- Journal Page Range
- 514-520
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 7. topical meeting on the technology of fusion energy.
- Dates
- 15-19 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18053913
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPACT IGNITION TOKAMAK; COOLING; ELECTROMAGNETIC RADIATION; FIRST WALL; GRAPHITE; HEAT FLUX; PLASMA DISRUPTION; SPECIFICATIONS; STRESS ANALYSIS; THERMAL ANALYSIS; THERMAL CONDUCTIVITY; THICKNESS; TIME DEPENDENCE; VACUUM SYSTEMS
- Descriptors DEC
- CARBON; CLOSED PLASMA DEVICES; DIMENSIONS; ELEMENTS; NONMETALS; PHYSICAL PROPERTIES; RADIATIONS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES
Optional Information
- Secondary number(s)
- CONF-860652--.