Fabrication constraints applied to the reactor physics design of the Advanced Neutron Source
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5854802
- Oak Ridge National Lab., TN (United States)
The Advanced Neutron Source (ANS) reactor, currently in the conceptual design stage, will provide neutrons for a variety of research and development tasks. The reactor concept and methods of analysis have been described. The current work presents the impact of fabrication restrictions on the {sup 235}U distribution within the core. Because the ANS reactor operates at a high power density (above 5 MW/{ell}), the concentration of {sup 235}U is varied radially and axially along the fuel elements to obtain an optimal power shape. The optimal shape is determined by several factors, including prevention of incipient boiling within the core and prevention of spallation of aluminum oxide from the fuel clad. The optimal radial power shape is for the profile to be flat. The optimal axial power shape is for the highest power density to be at the lower edge of the element with a linear decrease in power density as the height increases. The presence of control blades and their movement during the cycle inhibits attaining the optimal distribution.
- OSTI ID:
- 5854802
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ACTINIDE ISO
ACTINIDE NUCLEI
ALGORITHMS
ALPHA DECAY RADIOISOTOPES
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
CHALCOGENIDES
CROSS SECTIONS
DESIGN
EVEN-ODD NUCLEI
FABRICATION
FUEL ASSEMBLIES
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATHEMATICAL LOGIC
MINUTES LIVING RADIOISOTOPES
NEUTRON SOURCES
NUCLEAR DATA COLLECTIONS
NUCLEI
OPERATION
OXIDES
OXYGEN COMPOUNDS
PARTICLE SOURCES
PHYSICS
PLANNING
POWER DENSITY
RADIATION SOURCES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
SPONTANEOUS FISSION RADIOISOTOPES
URANIUM 235
URANIUM COMPOUNDS
URANIUM ISOTOPES
URANIUM OXIDES
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ACTINIDE ISO
ACTINIDE NUCLEI
ALGORITHMS
ALPHA DECAY RADIOISOTOPES
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
CHALCOGENIDES
CROSS SECTIONS
DESIGN
EVEN-ODD NUCLEI
FABRICATION
FUEL ASSEMBLIES
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATHEMATICAL LOGIC
MINUTES LIVING RADIOISOTOPES
NEUTRON SOURCES
NUCLEAR DATA COLLECTIONS
NUCLEI
OPERATION
OXIDES
OXYGEN COMPOUNDS
PARTICLE SOURCES
PHYSICS
PLANNING
POWER DENSITY
RADIATION SOURCES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
SPONTANEOUS FISSION RADIOISOTOPES
URANIUM 235
URANIUM COMPOUNDS
URANIUM ISOTOPES
URANIUM OXIDES