INTOR first wall/blanket/shield activity

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:6043607

Gohar, Y; Billone, M C; Cha, Y S; Finn, P A; Hassanein, A M; Liu, Y Y; Majumdar, S; Picologlou, B F; Smith, D L

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-31109-ENG-38
• OSTI ID: 6043607
• Report Number(s): CONF-860391-1; ON: DE86008004
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DESIGN
ECONOMICS
EMBRITTLEMENT
ENERGY TRANSFER
FERRITIC STEELS
FIRST WALL
FLUID MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TRANSFER
HYDRAULICS
HYDROGEN EMBRITTLEMENT
HYDROGEN ISOTOPES
INTOR TOKAMAK
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MATERIALS
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
RELIABILITY
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES