Thermal hydraulic analyses of two fusion reactor first wall/blanket concepts
A comparative study has been made of the thermal hydraulic performance of two liquid lithium blanket concepts for tokamak-type reactors. In one concept lithium is circulated through 60-cm deep cylindrical modules oriented so that the module axis is parallel to the reactor minor radius. In the other concept helium carrying channels oriented parallel to the first wall are used to cool a 60-cm thick stagnant lithium blanket. Paralleling studies were carried out wherein the thermal and structural properties of the construction materials were based on those projected for either solution-annealed 316-stainless steel or vanadium-base alloys. The effects of limitations on allowable peak structural temperature, material strength, thermal stress, coolant inlet temperature, and pumping power/thermal power ratio were evaluated. Consequences to thermal hydraulic performance resulting from the presence of or absence of a divertor were also investigated.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5182798
- Report Number(s):
- CONF-771029-178; TRN: 78-006398
- Resource Relation:
- Conference: 7. symposium on fusion research project, Knoxville, TN, USA, 25 Oct 1977
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
STAINLESS STEEL-316
THERMAL STRESSES
THERMONUCLEAR REACTOR WALLS
HYDRAULICS
THERMODYNAMIC PROPERTIES
VANADIUM BASE ALLOYS
BREEDING BLANKETS
DIVERTORS
FIRST WALL
THERMODYNAMICS
TOKAMAK TYPE REACTORS
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
STAINLESS STEELS
STEELS
STRESSES
THERMONUCLEAR REACTORS
VANADIUM ALLOYS
700201* - Fusion Power Plant Technology- Blanket Engineering