Prompt and delayed radiation shielding calculations for the zephyr deuterium-tritium ignition experiment

Journal Article · Thu Apr 01 00:00:00 UTC 1982 · Nucl. Technol./Fusion; (United States)

OSTI ID:5593002

Prillinger, G; Fischer, A; Fischer, E; Krause,

Results of discrete ordinates radiation transport calculations are presented for the proposed tokamak ignition and burn control experiment ZEPHYR. As a first step, baryte concrete with 0.15 wt% B/sub 4/C was identified as an optimum concrete for the shielding fitting tightly around the torus and some attached devices. This shielding material with a maximum thickness of 70 cm allows personnel to enter the experiment hall just a few hours after termination of a worst-case burn discharge sequence. Inside the vacuum vessel, delayed dose rates amount to several tens of rem/h after only 50 s of plasma burn for waiting times that are typical for maintenance and repair, thus, remote handling equipment is required. Bootstrapped radiation transport calculations for neutral beam injectors show them to be strongly activated after the worst-case discharge sequence with typical dose rates of some rem/h. Thus shielding is required around the injector boxes and most repair tasks have to be performed remotely. Delayed dose rates outside the torus shielding in front of typical straight diagnostic ducts with diameters of 15 to 25 cm are shown to be significant but ''hands-on'' maintenance of the diagnostic equipment will be possible with some restrictions on working time.

• Research Organization: Institut fur Kernenergetik und Energiesysteme, Universitat Stuttgart, D-7000 Stuttgart
• DOE Contract Number: NONE
• OSTI ID: 5593002
• Journal Information: Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 2:2; ISSN NTFUD
• Country of Publication: United States
• Language: English

Related Subjects

654002* -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200 -- Fusion Energy-- Fusion Power Plant Technology
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BEAM INJECTION
BUILDING MATERIALS
CALCULATION METHODS
CONCRETES
DOSE RATES
EPITHERMAL REACTORS
EQUIPMENT
EXPERIMENTAL REACTORS
FAST REACTORS
IRRADIATION REACTORS
MAINTENANCE
MATERIALS
MATERIALS HANDLING EQUIPMENT
MATERIALS TESTING REACTORS
NATURAL URANIUM REACTORS
NEUTRAL ATOM BEAM INJECTION
NEUTRAL PARTICLES
NEUTRAL-PARTICLE TRANSPORT
PARTICLES
PLUTONIUM REACTORS
RADIATION STREAMING
RADIATION TRANSPORT
REACTOR MAINTENANCE
REACTORS
REMOTE HANDLING EQUIPMENT
RESEARCH AND TEST REACTORS
SHIELDING
SHIELDING MATERIALS
THERMONUCLEAR IGNITION
ZEPHYR REACTOR
ZERO POWER REACTORS