Results of parametric neutronic studies for high-temperature blankets with breeding
Previous conceptual studies have been extended to examine a wide range of possible blanket configurations. The overall goals of this study have been to achieve neutronically viable blanket combinations that obtain an average breeding ratio (BR) of at least 1.1 and a sufficiently high fraction of fusion energy, Q/sub FRAC//sup HI/ (20% HTE High Temperature Heat) in the HTE process steam. The present studies have converged on the most attractive blanket option. After a preliminary and a secondary round of parametric calculations, ZrO/sub 2/ was selected as the best ceramic material; and a shell design with a flux trap type of back breeding zone with a Zr or Graphite plug, was chosen as optimal for the HTE module.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6762960
- Report Number(s):
- BNL-28903; CONF-810606-10; TRN: 81-009053
- Resource Relation:
- Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
BREEDING
NEUTRON TRANSPORT
ALUMINIUM OXIDES
LITHIUM OXIDES
PARAMETRIC ANALYSIS
PROCESS HEAT
ZIRCONIUM OXIDES
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
CHALCOGENIDES
ENERGY
HEAT
LITHIUM COMPOUNDS
NEUTRAL-PARTICLE TRANSPORT
NUCLEAR FUEL CONVERSION
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
REACTOR COMPONENTS
TRANSITION ELEMENT COMPOUNDS
ZIRCONIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering