INTOR first wall/blanket/shield activity
The main emphasis of the INTOR first wall/blanket/shield (FWBS) during this period has been upon the tritium breeding issues. The objective is to develop a FWBS concept which produces the tritium requirement for INTOR operation and uses a small fraction of the first wall surface area. The FWBS is constrained by the dimensions of the reference design and the protection criteria required for different reactor components. The blanket extrapolation to commercial power reactor conditions and the proper temperature for power extraction have been sacrificed to achieve the highest possible local tritium breeding ratio (TBR). In addition, several other factors that have been considered in the blanket survey study include safety, reliability, lifetime fluence, number of burn cycles, simplicity, cost, and development issues. The implications of different tritium supply scenarios were discussed from the cost and availability for INTOR conditions. A wide variety of blanket options was explored in a preliminary way to determine feasibility and to see if they can satisfy the INTOR conditions. This survey and related issues are summarized in this report. Also discussed are material design requirements, thermal hydraulic considerations, structure analyses, tritium permeation through the first wall into the coolant, and tritium inventory.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6043607
- Report Number(s):
- CONF-860391-1; ON: DE86008004
- Resource Relation:
- Conference: INTOR workshop, Vienna, Austria, 10 Mar 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
INTOR TOKAMAK
FIRST WALL
BREEDING BLANKETS
DESIGN
ECONOMICS
FERRITIC STEELS
HEAT TRANSFER
HYDRAULICS
HYDROGEN EMBRITTLEMENT
RELIABILITY
STAINLESS STEEL-316
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EMBRITTLEMENT
ENERGY TRANSFER
FLUID MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MATERIALS
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties