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Radioactivity in the light ion fusion Target Development Facility

Conference · · Fusion Technol.; (United States)
OSTI ID:6009085
; ;
Radioactivity and biological dose calculations have been performed for the target chamber of the Target Development Facility (TDF). Two conventional shield designs are considered. One has the target chamber submerged 3 m from the surface of a borated water pool, the other has the chamber surrounded by approximately 250 cm of concrete. The first wall materials, Al-6061 and 2-1/4 Cr-1 Mo steel and the ion beam targets, one made from BeO/sub 2/ and W and the other from CH/sub 2/ and Au, are investigated. Shielding designs are presented that reduce the dose from each of these choices of shield, first wall and target material to acceptable levels.
Research Organization:
Nuclear Engineering Department, University of Wisconsin, Madison, WI
OSTI ID:
6009085
Report Number(s):
CONF-850310-
Conference Information:
Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCELERATOR FACILITIES
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
BERYLLIUM COMPOUNDS
BERYLLIUM OXIDES
BIOLOGICAL SHIELDING
BIOLOGICAL SHIELDS
BORATES
BORON COMPOUNDS
BUILDING MATERIALS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CONCRETES
DESIGN
DOSES
ELEMENTS
ION BEAM FUSION REACTORS
ION BEAM TARGETS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
METALS
OXIDES
OXYGEN COMPOUNDS
RADIATION DOSES
RADIATION PROTECTION
RADIOACTIVITY
SHIELDING
SHIELDING MATERIALS
SHIELDS
STEELS
TARGET CHAMBERS
TARGETS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
TUNGSTEN