Engineering design of a liquid metal cooled self-pumped limiter for a tokamak reactor [electronic resource].
- Published:
- Argonne, Ill. : Argonne National Laboratory, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 5 : digital, PDF file
- Additional Creators:
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- A lithium cooled self-pumped limiter has been designed as the impurity control system for the TPSS high-..beta.. power reactor conceptual design. The limiter removes helium by trapping impinging helium ions in freshly deposited vanadium surface layers in a slot region. No hydrogen is removed and no pumps or vacuum penetrations are used, thereby eliminating penetration shielding and reducing tritium handling. The limiter is composed of a vanadium alloy structure with a 2mm tungsten cladding on the front face and leading edges for sputtering control. Up to approx.3cm of vanadium trapping material is deposited in the slot region during 5 years of operation. A key design feature is the use of a calcium oxide electrical insulator which coats the limiter coolant channels to reduce MHD pressure drops. A combination of high lithium coolant velocity, made possible by the insulator, and mid-limiter manifolding has been used to obtain acceptable material temperatures with moderately high heat fluxes (3 to 5 mw/m/sup 2/). Overall, a limiter lifetime of approx.5 years is predicted by stress and lifetime analysis. This would permit maintenance free impurity control operation between first wall/blanket replacement periods. 4 refs., 3 figs., 1 tab.
- Report Numbers:
- E 1.99:conf-871007-67
conf-871007-67 - Subject(s):
- Other Subject(s):
- Tokamak Type Reactors
- Pumped Limiters
- Thermonuclear Reactor Cooling Systems
- Design
- First Wall
- Heat Flux
- Heat Transfer
- Insolation
- Liquid Metals
- Lithium
- Stress Analysis
- Thermal Analysis
- Vanadium Alloys
- Alkali Metals
- Alloys
- Cooling Systems
- Elements
- Energy Systems
- Energy Transfer
- Fluids
- Limiters
- Liquids
- Metals
- Thermonuclear Reactor Walls
- Thermonuclear Reactors
- Note:
- Published through SciTech Connect.
10/01/1987.
"conf-871007-67"
"DE88002845"
12. symposium on fusion engineering, Monterey, CA, USA, 12 Oct 1987.
Smith, D.L.; Brooks, J.N.; Cha, Y.; Hassanein, A.; Majumdar, S.; Mattas, R.F. - Funding Information:
- W-31109-ENG-38
View MARC record | catkey: 14753367