Neutronics performance of a helium-cooled solid breeder blanket and shield for ITER
A neutronics analysis of a helium gas-cooled Li/sub 4/SiO/sub 4/ solid breeder blanket for the International Thermonuclear Experimental Reactor (ITER) has been performed. The 60 cm thick breeder blanket placed in the outboard zone of the tokamak is composed of beryllium and solid breeder (SB) rods. The rods are arranged so that homogeneity of Be and SB is realized as much as possible. Helium gas is utilized as both main coolant and purge flow for tritium extraction. The blanket is followed by a carbon reflector and a B/sub 4/C/PCA shield. The 48 cm-thick inboard shield consists of multi-layers of W and ZrH/sub 2/ cooled by helium gas. A Be layer of thickness 4.89 cm is added in the front of the shield to enhance the tritium breeding in the outboard blanket. Extensive 1-D analysis revealed an optimum configuration of the breeder resulting in a tritium breeding ratio (TBR) of 1.35 when 90% /sup 6/Li enriched material is used. A subsequent 3-D analysis of the optimized blanket demonstrated that a TBR of unity is achievable in the 6 m-height outboard blanket. By adding the breeder in the top and bottom zones of the reactor, the TBR can be as large as 1.2.
- Research Organization:
- Univ. of California, Los Angeles, Los Angeles, CA (US)
- OSTI ID:
- 6244768
- Report Number(s):
- CONF-881031-; TRN: 89-013928
- Journal Information:
- Fusion Technol.; (United States), Vol. 15:2; Conference: 8. topical meeting on technology of fusion energy, Salt Lake City, UT, USA, 9 Oct 1988
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
SHIELDS
TOKAMAK DEVICES
ACTIVATION ANALYSIS
BERYLLIUM
BREEDING RATIO
EXPERIMENTAL REACTORS
HELIUM
INTERNATIONAL COOPERATION
LITHIUM 6
NEUTRON TRANSPORT
OPTIMIZATION
THERMONUCLEAR REACTOR MATERIALS
THREE-DIMENSIONAL CALCULATIONS
TRITIUM EXTRACTION PLANT
TUNGSTEN
ZIRCONIUM HYDRIDES
ALKALI METAL ISOTOPES
ALKALINE EARTH METALS
CHEMICAL ANALYSIS
CLOSED PLASMA DEVICES
CONVERSION RATIO
COOPERATION
ELEMENTS
FLUIDS
GASES
HYDRIDES
HYDROGEN COMPOUNDS
INDUSTRIAL PLANTS
ISOTOPE SEPARATION PLANTS
ISOTOPES
LIGHT NUCLEI
LITHIUM ISOTOPES
MATERIALS
METALS
NEUTRAL-PARTICLE TRANSPORT
NONMETALS
NUCLEAR FACILITIES
NUCLEI
ODD-ODD NUCLEI
RADIATION TRANSPORT
RARE GASES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
STABLE ISOTOPES
THERMONUCLEAR DEVICES
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
ZIRCONIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering
700206 - Fusion Power Plant Technology- Environmental Aspects
700205 - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems