Monte Carlo methods, models, and applications for the Advanced Neutron Source
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6023697
- Idaho National Energy Lab., Idaho Falls (USA)
A three-dimensional, continuous-energy, coupled neutron-gamma Monte Carlo model of the advanced neutron source (ANS) final preconceptual reference core design has been developed using MCNP Version 3b. This model contains the reactor core with control rods, the heavy-water reflector tank with shutdown rods and representative beam tubes, and the outer light-water poor. Eighty homogenized fuel zones per fuel element are used to represent the radical and axial {sup 235}U fuel grading. This model is the most sophisticated, physically accurate reactor physics model of the ANS currently available. The purpose of this summary is to demonstrate the MCNP methods and applications for the ANS.
- OSTI ID:
- 6023697
- Report Number(s):
- CONF-900608--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
ACCURACY
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
COMPARATIVE EVALUATIONS
COMPUTER CODES
CONTROL ELEMENTS
CROSS SECTIONS
DESIGN
EFFICIENCY
ELEMENTARY PARTICLES
ERRORS
EVEN-ODD NUCLEI
FERMIONS
FISSION PRODUCTS
FUEL ELEMENTS
HADRONS
HEAVY NUCLEI
IRRADIATION
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
M CODES
MATERIALS
MINUTES LIVING RADIOISOTOPES
MONTE CARLO METHOD
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON REFLECTORS
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEI
NUCLEONS
PARTICLE SOURCES
PHYSICS
PLANNING
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SCRAM RODS
THERMAL NEUTRONS
TRANSPORT THEORY
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
ACCURACY
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
COMPARATIVE EVALUATIONS
COMPUTER CODES
CONTROL ELEMENTS
CROSS SECTIONS
DESIGN
EFFICIENCY
ELEMENTARY PARTICLES
ERRORS
EVEN-ODD NUCLEI
FERMIONS
FISSION PRODUCTS
FUEL ELEMENTS
HADRONS
HEAVY NUCLEI
IRRADIATION
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
M CODES
MATERIALS
MINUTES LIVING RADIOISOTOPES
MONTE CARLO METHOD
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON REFLECTORS
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEI
NUCLEONS
PARTICLE SOURCES
PHYSICS
PLANNING
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SCRAM RODS
THERMAL NEUTRONS
TRANSPORT THEORY
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES