Overview of INTOR nuclear systems

Conference · Thu Jan 01 04:00:00 EST 1981 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6482156

Abdou, M A

A serious effort was devoted in the Phase-1 study for INTOR to identifying critical issues and developing credible design concepts for the nuclear systems. Erosion by charge-exchange neutrals and effects of plasma disruption are key issues for the first wall. A melt layer is predicted to develop in a bare stainless steel wall under plasma disruptions. Graphite tiles will not melt but they introduce serious uncertainties into the design. A partial tritium-producing blanket will be installed on INTOR to reduce the cost of externally supplied tritium. The key issue is the solid breeder blanket concept relates to the effect of radiation on tritium inventory in the blanket. The design strategy for the divertor collector plate focused on separating the surface and high heat flux problems and on utilizing a novel mechanical design concept for attaching tungsten tiles to a stainless steel (or copper) heat sink.

• Research Organization: Argonne Natl Lab, IL, USA
• OSTI ID: 6482156
• Report Number(s): CONF-811040-
• Conference Information: Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States)
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
DESIGN
DIVERTORS
ENGINEERING
FIRST WALL
HYDROGEN ISOTOPES
INTOR TOKAMAK
ISOTOPES
LIGHT NUCLEI
NUCLEAR ENGINEERING
NUCLEI
ODD-EVEN NUCLEI
POLOIDAL DIVERTORS
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES