Published July 1985
| Version v1
Journal article
Advanced inboard shielding design for Tokamak fusion reactors
Creators
- 1. Fusion Technology Institute, University of Wisconsin-Madison, Madison, WI
Description
The recent physics and technology advances in the field of high power density compact tokamak reactors have established the need for advanced inboard shielding design. This work presents the design of an optimal inboard shield and assesses the limits on the radiation effects in the magnets of a high wall loading (10 MW/m2) tokamak design. A new material, boron hydride, was identified as a potential shielding material and more optimum combinations of TiH2, B4C, and W were identified as well
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 8
- Journal Issue
- 1
- Series
- Fusion Technol.
- Journal Page Range
- 1037-1042
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 6. topical meeting on the technology of fusion energy.
- Dates
- 3-7 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17080206
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORANES; BORON CARBIDES; LIMITING VALUES; MATERIALS TESTING; PHYSICAL RADIATION EFFECTS; SHIELDING; SHIELDING MATERIALS; SHIELDS; THERMONUCLEAR REACTOR MATERIAL; THERMONUCLEAR REACTORS; TITANIUM HYDRIDES; TOKAMAK DEVICES; TUNGSTEN; WALL LOADING
- Descriptors DEC
- BORON COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CLOSED PLASMA DEVICES; ELEMENTS; HYDRIDES; HYDROGEN COMPOUNDS; MATERIALS; METALS; POWER DENSITY; RADIATION EFFECTS; TESTING; THERMONUCLEAR DEVICES; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS
Optional Information
- Secondary number(s)
- CONF-850310--.