Energy deposition and shielding requirements for all concepts of the Blanket Comparison and Selection Study
The Blanket Comparison and Selection Study (BCSS) carried out 16 blanket concepts (7 tokamaks and 9 tandem mirror reactors (TMRs)) for the final evaluation process. This process requires all the blanket design parameters, including the energy multiplication factors, the atomic displacement rate in the first wall, and the shielding definition for the reactor. A shielding assessment is performed to determine shielding materials, compositions, arrangements, and thicknesses for each concept. Two shielding criteria are adopted for this assessment: (a) workers are permitted in the reactor hall 1 day after shutdown, and (b) superconductor coils are required to function for a 150 MW x yr/m/sup 2/ deuterium-tritium neutron exposure at the first wall without a change in their performances. For the design purpose, the occupational exposure is 0.5 mrem/h, based on working 8 h/day and 40 h/week. This dose level is used to concur with current practice in the nuclear industry and the exposure policy of the U.S. Department of Energy, which limits the on-site personnel exposure level to less than onefifth of the maximum permissible dose equivalent limits. The personnel exposure criterion is used to size the outboard bulk shield for tokamak reactors and the shield thickness between the central cell coils for TMRs. In the fusion power environment the insulator materials are the most sensitive components in the superconductor coils from the radiation damage point of view. A maximum insulator dose of 10/sup 10/ rad in the thermal insulator is used to size the bulk shield in the inboard section of the tokamak reactors and the central cell sections under the coils for TMRs. As a result of this criterion, all other nuclear responses do not exceed any design limit for the superconductor materials or the copper stabilizer.
- Research Organization:
- Argonne National Laboratory, Argonne, IL
- OSTI ID:
- 6011402
- Journal Information:
- Fusion Technol.; (United States), Vol. 8:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
DESIGN
ENERGY ABSORPTION
PHYSICAL RADIATION EFFECTS
SHIELDING
TMR REACTORS
TOKAMAK TYPE REACTORS
DOSE LIMITS
ENERGY LOSSES
FIRST WALL
MULTIPLICATION FACTORS
NEUTRON FLUENCE
RADIATION PROTECTION
SHIELDS
SUPERCONDUCTING COILS
THERMONUCLEAR REACTOR MATERIALS
THICKNESS
ABSORPTION
DIMENSIONS
LOSSES
MAGNETIC MIRROR TYPE REACTORS
MATERIALS
RADIATION EFFECTS
REACTOR COMPONENTS
SAFETY STANDARDS
STANDARDS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing