US INTOR radiation-shield design
The US analysis for the INTOR radiation-shield design focused on three areas. First, a careful optimization process for the inboard shield composition and material arrangement within the allowable radial shield thickness was performed to minimize the radiation effects in the toroidal field (TF) coils. The TF coils are designed to last the lifetime of the reactor without change in performance. Second, the outboard bulk shield composition and material arrangement were optimized to achieve a dose equivalent outside the bulk shield of less than or equal to 2.5 mrem/h within one day after shutdown to permit personnel access to the reactor hall. Third, the penetration shields were designed to satisfy the same requirements as the outboard bulk shield.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5588460
- Report Number(s):
- CONF-830538-18; ON: DE83017912
- Resource Relation:
- Conference: 6. international conference on radiation shielding, Tokyo, Japan, 16 May 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
INTOR TOKAMAK
SHIELDING
DESIGN
BREEDING BLANKETS
MAGNET COILS
PERFORMANCE
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing