Natural uranium hybrid blankets for the Ayman project
Conference
·
· Alternative Energy Sources; (United States)
OSTI ID:6565123
In the framework of the AYMAN fusion-fission (hybrid) experimental reactor project, a series of calculations have been performed in order to evaluate the optimal parameters to prepare sufficient information prior to final decision for the design work. A potential experimental hybrid blanket may contain natural - UO/sub 2/ - fuel. This study searches the design parameters for two types of hybrid blankets: a. Blankets with a high energy multiplication factor M to burn the fissile fuel in situ representing a power generating hybrid reactor complex. b. Blankets with a high fissile and fusile breeding capability, representing a hybrid reactor, designed as a fuel factory. Li will be used as tritium breeder in the early phase of investigations. The investigated experimental hybrid blankets, in cylinderical geometry, consist of the following components: 1) Plasma chamber with a radius of 38.7 cm 2) First wall: SS-316, 1.3 cm, corresponding to the first wall of TFTR.
- Research Organization:
- King Saud Univ., Riyadh
- OSTI ID:
- 6565123
- Report Number(s):
- CONF-831205-
- Conference Information:
- Journal Name: Alternative Energy Sources; (United States)
- Country of Publication:
- United States
- Language:
- English
Similar Records
Advanced fusion fuel driven AYMAN hybrid blankets
(D,T) Driven thorium hybrid blankets
Neutronics analysis of deuterium-tritium-driven experimental hybrid blankets
Conference
·
Wed Nov 30 23:00:00 EST 1983
· Alternative Energy Sources; (United States)
·
OSTI ID:6578697
(D,T) Driven thorium hybrid blankets
Conference
·
Wed Nov 30 23:00:00 EST 1983
· Alternative Energy Sources; (United States)
·
OSTI ID:6853512
Neutronics analysis of deuterium-tritium-driven experimental hybrid blankets
Journal Article
·
Sun Jul 01 00:00:00 EDT 1984
· Fusion Technol.; (United States)
·
OSTI ID:5509933
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE COMPOUNDS
ALKALI METALS
BREEDING BLANKETS
CALCULATION METHODS
CHALCOGENIDES
CONFIGURATION
CYLINDRICAL CONFIGURATION
DESIGN
ELEMENTS
ENERGY SOURCES
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUELS
FUNCTIONAL MODELS
HYBRID REACTORS
IN-SITU PROCESSING
LITHIUM
MATERIALS
METALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PILOT PLANTS
PROCESSING
REACTOR COMPONENTS
REACTOR MATERIALS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE COMPOUNDS
ALKALI METALS
BREEDING BLANKETS
CALCULATION METHODS
CHALCOGENIDES
CONFIGURATION
CYLINDRICAL CONFIGURATION
DESIGN
ELEMENTS
ENERGY SOURCES
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUELS
FUNCTIONAL MODELS
HYBRID REACTORS
IN-SITU PROCESSING
LITHIUM
MATERIALS
METALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PILOT PLANTS
PROCESSING
REACTOR COMPONENTS
REACTOR MATERIALS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES