Blanket comparison and selection study. Final report. Volume 2
The study focused on: (1) Development of reference design guidelines, evaluation criteria, and a methodology for evaluating and ranking candidate blanket concepts. (2) Compilation of the required data base and development of a uniform systems analysis for comparison. (3) Development of conceptual designs for the comparative evaluation. (4) Evaluation of leading concepts for engineering feasibility, economic performance, and safety. (5) Identification and prioritization of R and D requirements for the leading blanket concepts. Sixteen concepts (nine TMR and seven tokamak) which were identified as leading candidates in the early phases of the study, were evaluated in detail. The overall evaluation concluded that the following concepts should provide the focus for the blanket R and D program: (Breeder/Coolant/Structure), Lithium/Lithium/Vanadium Alloy, Li/sub 2/O/Helium/Ferritic Steel, LiPb Alloy/LiPb Alloy/Vanadium Alloy, and Lithium/Helium/Ferritic Steel. The primary R and D issues for the Li/Li/V concept are the development of an advanced structural alloy, resolution of MHD and corrosion problems, provision for an inert atmosphere (e.g., N/sub 2/) in the reactor building, and the development of non-water cooled near-plasma components, particularly for the tokamak. The main issues for the LiPb/LiPb/V concepts are similar to the Li/Li/V blanket with the addition of resolving the tritium recovery issue. The R and D issues for Li/sub 2/O/He/FS concept include resolution of the tritium recovery/containment issue, achieving adequate tritium breeding and resolving other solid breeder issues such as swelling and fabrication concerns. Major concerns for the Li/He/FS concept are related to its rather poor economic performance. Improvement of its economic performance will be somewhat concept-dependent and will be more of a systems engineering issue.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6084844
- Report Number(s):
- ANL/FPP-84-1-Vol.2; ON: DE85005867
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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ALLOY-HT-9
CORROSION
AUSTENITIC STEELS
BREEDING BLANKETS
COMPARATIVE EVALUATIONS
DESIGN
LITHIUM
CORROSIVE EFFECTS
VANADIUM BASE ALLOYS
BREEDING
COMPATIBILITY
FLIBE
MAGNETOHYDRODYNAMICS
NITRATES
OXIDATION
PHYSICAL PROPERTIES
RADIOACTIVATION
THERMODYNAMIC PROPERTIES
TRITIUM
ALKALI METALS
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
ELEMENTS
FLUID MECHANICS
HYDRODYNAMICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MECHANICS
METALS
MOLTEN SALTS
NITROGEN COMPOUNDS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
RADIOISOTOPES
REACTOR COMPONENTS
SALTS
STEELS
VANADIUM ALLOYS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering