Safeguard aspects of sup 244 Cm as a multiplier in cylindrical hybrid blankets
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6799805
Presently, nuclear power plants are producing substantial amounts of actinides in the form of nuclear waste material. Previous work has demonstrated that some of the nuclear waste actinides, such as {sup 241}Am and {sup 244}Cm, are effective neutron multipliers in a hybrid blanket. They will be converted, partially, to new types of nuclear fuel wit superior neutronic properties, such as {sup 242m}Am and {sup 245}Cm. In this work, the neutron multiplication and breeding performance of {sup 244}Cm is analyzed in connection with a deuterium-tritium (D-T)-driven experimental hybrid blanket in cylindrical geometry within the research program AYMAN in order to simulate relatively realistic neutron spectra for future hybrid reactors. Four blanket configurations with different multipliers are investigated for comparison. In all configurations, the ThO{sub 2} fuel zone is 13 cm, making 10 rows in hexagonal range. The {sup 244}Cm multiplier is introduced by replacing the first ThO{sub 2} row with a mixed fuel made of 50% CmO{sub 2} and 50% ThO{sub 2}. One can observe that a {sup 244}Cm multiplier leads to the highest tritium breeding ratio. Uranium-233 production is reduced compared to beryllium and lead multipliers. The 50% {sup 244}Cm in the first row contributes to the fission rate more than all of the {sup 232}Th in the blanket. About 20% of the {sup 244}Cm is converted into {sup 245}Cm, while 80% of the {sup 244}Cm burns up. 14 refs., 1 fig., 1 tab.
- OSTI ID:
- 6799805
- Report Number(s):
- CONF-860610--Summs.
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
Similar Records
CM-244 as multiplier and breeder in a ThO/sub 2/ hybrid blanket driven by a (D,T) source
Neutronics analysis of deuterium-tritium-driven experimental hybrid blankets
Safeguard aspects of /sup 244/Cm as a multiplier in cylindrical hybrid blankets
Conference
·
Fri Oct 31 23:00:00 EST 1986
· Fusion Technol.; (United States)
·
OSTI ID:7005772
Neutronics analysis of deuterium-tritium-driven experimental hybrid blankets
Journal Article
·
Sun Jul 01 00:00:00 EDT 1984
· Fusion Technol.; (United States)
·
OSTI ID:5509933
Safeguard aspects of /sup 244/Cm as a multiplier in cylindrical hybrid blankets
Conference
·
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· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5539029
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
A CODES
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BARYONS
BREEDING BLANKETS
BREEDING RATIO
CHALCOGENIDES
COMPUTER CODES
CONVERSION RATIO
CURIUM 244
CURIUM ISOTOPES
DATA
ELEMENTARY PARTICLES
EVEN-EVEN NUCLEI
FERMIONS
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUELS
HADRON REACTIONS
HADRONS
HEAVY NUCLEI
HYBRID REACTORS
INFORMATION
ISOTOPES
MATERIALS
MULTIPLICATION FACTORS
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
RADIOISOTOPES
REACTOR COMPONENTS
THEORETICAL DATA
THERMONUCLEAR FUELS
THORIUM COMPOUNDS
THORIUM OXIDES
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
A CODES
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BARYONS
BREEDING BLANKETS
BREEDING RATIO
CHALCOGENIDES
COMPUTER CODES
CONVERSION RATIO
CURIUM 244
CURIUM ISOTOPES
DATA
ELEMENTARY PARTICLES
EVEN-EVEN NUCLEI
FERMIONS
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUELS
HADRON REACTIONS
HADRONS
HEAVY NUCLEI
HYBRID REACTORS
INFORMATION
ISOTOPES
MATERIALS
MULTIPLICATION FACTORS
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
RADIOISOTOPES
REACTOR COMPONENTS
THEORETICAL DATA
THERMONUCLEAR FUELS
THORIUM COMPOUNDS
THORIUM OXIDES
YEARS LIVING RADIOISOTOPES