Fusion breeder reactor based on a catalyzed D-D spherical torus. Final report, 8 August 1986
Technical Report
·
OSTI ID:7127357
One of the potentially attractive applications of nuclear fusion is to breed fissile fuel for use in fission reactors. This thesis examines a novel nonpower-producing fusion reactor based on the spherical torus concept with a catalyzed deuterium-deuterium fuel cycle and aqueous self-cooled blanket for use as a fissile breeder. The breeding of fissile fuel is accomplished by dissolving a uranium salt, uranyl nitrite, in heavy water which flows through the first wall and blanket providing both cooling and fissile breeding. The need for tritium breeding is eliminated by the use of a catalyzed D-D fuel cycle. Analysis of this novel reactor concept indicates a fissile breeding ratio of 1.34 Pu-239/source neutron using a 15-cm beryllium moderator and 7 mo1% uranyl nitrite in the heavy water. A typical reactor using this blanket can produce more than 8000 kg/yr of plutonium at a cost of less than $40 per gram. This indicates the potential for a reactor which can provide fissile fuel at, or below, its current mined cost.
- Research Organization:
- Army Military Personnel Center, Alexandria, VA (USA)
- OSTI ID:
- 7127357
- Report Number(s):
- AD-A-173879/8/XAB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
BREEDING BLANKETS
CLADDING
DEPOSITION
DEUTERIUM
EFFICIENCY
ELEMENTS
ENERGY SOURCES
EVEN-ODD NUCLEI
FISSIONABLE MATERIALS
FUEL CYCLE
FUELS
HEAVY NUCLEI
HEAVY WATER
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
METALS
NUCLEAR FUELS
NUCLEI
ODD-ODD NUCLEI
OXYGEN COMPOUNDS
PLUTONIUM
PLUTONIUM 239
PLUTONIUM ISOTOPES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
STABLE ISOTOPES
SURFACE COATING
THERMONUCLEAR REACTORS
TORI
TRANSURANIUM ELEMENTS
URANIUM COMPOUNDS
WATER
YEARS LIVING RADIOISOTOPES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
BREEDING BLANKETS
CLADDING
DEPOSITION
DEUTERIUM
EFFICIENCY
ELEMENTS
ENERGY SOURCES
EVEN-ODD NUCLEI
FISSIONABLE MATERIALS
FUEL CYCLE
FUELS
HEAVY NUCLEI
HEAVY WATER
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
METALS
NUCLEAR FUELS
NUCLEI
ODD-ODD NUCLEI
OXYGEN COMPOUNDS
PLUTONIUM
PLUTONIUM 239
PLUTONIUM ISOTOPES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
STABLE ISOTOPES
SURFACE COATING
THERMONUCLEAR REACTORS
TORI
TRANSURANIUM ELEMENTS
URANIUM COMPOUNDS
WATER
YEARS LIVING RADIOISOTOPES