Conceptual design of the tokamak radiation shielding for the Tokamak Physics Experiment (TPX)
- 1. Oak Ridge National Lab., TN (United States)
- 2. Argonne National Lab., IL (United States)
- 3. Princeton Univ., NJ (United States). Plasma Physics Lab.
Description
The tokamak radiation shielding includes the neutron and gamma shielding around the torus and penetrations required to (1) limit activation of components outside the shield to levels that permit hands-on maintenance and (2) limit the nuclear heating of the superconducting coils and cold structure. The primary design drivers are space, the 350 degree C bakeout temperature, and cost; therefore, different shield materials were used for different shield components and locations. The shielding is divided into three areas: (1) torus shielding around the vacuum vessel, (2) duct shielding around the vacuum pumping ducts and vertical diagnostic ducts, and (3) penetration shielding in and around the radial ports. The major shield components include water between the walls of the vacuum vessel, lead monosilicate/boron carbide tiles that are attached to the exterior of the vacuum vessel, shield plugs that rill the openings of the large radial ports, and polyethylene/lead/boron shield blocks for duct shielding. A description of the shielding configuration and the performance and operational requirements will be discussed
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94002791; NTIS; US Govt. Printing Office Dep.Files
25030031.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CONF-931018--52
Conference
- Title
- Symposium on fusion engineering.
- Dates
- 11-15 Oct 1993.
- Place
- Hyannis, MA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25030031
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; DOSE RATES; PERFORMANCE; RADIATION PROTECTION; SHIELDING; SUPERCONDUCTING COILS; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (United States).