Design and analysis of the Solid Breeder Integral Simulation Test for PE-II
The PE-II Solid Breeder Concept Integral Simulation Test is designed to simulate (by way of nonnuclear heating) the thermal-hydraulic/ thermomechanical operating characteristics of a water-cooled, Li/sub 2/O fusion reactor blanket. The test piece consists of a central coolant tube surrounded by a cylinder of solid breeder material. This test piece, which simulates a unit cell of a blanket, is then subjected to an external heat flux and a purge flow of helium at carefully controlled conditions. Instrumentation provides information on temperature profiles, moisture levels, and purge flow conditions. Pretest thermal/stress analysis of this experiment indicates that it can provide an accurate simulation of actual conditions in a prototypical fusion reactor blanket.
- Research Organization:
- EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, ID 83415
- OSTI ID:
- 6185951
- Report Number(s):
- CONF-830406-
- Journal Information:
- Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 4:2; ISSN NTFUD
- Country of Publication:
- United States
- Language:
- English
Similar Records
Final report on PE-II activities from August 1981-September 1983
Breeder-in-tube design for a helium-cooled Li/sub 2/O tokamak blanket
Related Subjects
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METAL COMPOUNDS
BREEDING BLANKETS
CHALCOGENIDES
ELEMENTS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
FLUIDS
GASES
HEAT FLUX
HEAT TRANSFER
HELIUM
HYDRAULICS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MECHANICS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
RARE GASES
REACTOR COMPONENTS
SIMULATION
STRESS ANALYSIS
TESTING
THERMAL ANALYSIS
THERMAL CYCLING
THERMONUCLEAR REACTOR MATERIALS
TUBES