Radiation transport calculation for the ANS (advanced neutron source) beam tubes
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6126282
- Kyoto Univ. (Japan)
- Osaka Univ. (Japan)
- Oak Ridge National Lab., TN (USA)
The advanced neutron source (ANS) facility will incorporate a large number of beam tubes to provide very large thermal neutron fluxes to experimental facilities. The purpose of this work was to obtain angular fluxes of the thermal and fast neutron and gamma ray in a beam tube for the ANS intermediate reference core E3 (final preconceptual core geometry with the E3 version of fuel grading). In this paper, the coupled two-dimensional radiation transport calculations employed to estimate the angular neutron and gamma-ray fluxes are described, and the results from these calculations are discussed.
- OSTI ID:
- 6126282
- 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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Radiation transport calculations for the ANS (Advanced Neutron Source) beam tubes
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
BARYONS
BEAM HOLES
BEAM PRODUCTION
CALCULATION METHODS
COMPUTER CODES
CROSS SECTIONS
D CODES
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
GEOMETRY
HADRONS
HEAVY WATER
HYDROGEN COMPOUNDS
MATHEMATICS
MODERATORS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUCLEONS
OXYGEN COMPOUNDS
PARTICLE SOURCES
PLANNING
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SCALARS
SHIELDING
THERMAL NEUTRONS
TWO-DIMENSIONAL CALCULATIONS
WATER
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
BARYONS
BEAM HOLES
BEAM PRODUCTION
CALCULATION METHODS
COMPUTER CODES
CROSS SECTIONS
D CODES
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
GEOMETRY
HADRONS
HEAVY WATER
HYDROGEN COMPOUNDS
MATHEMATICS
MODERATORS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUCLEONS
OXYGEN COMPOUNDS
PARTICLE SOURCES
PLANNING
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SCALARS
SHIELDING
THERMAL NEUTRONS
TWO-DIMENSIONAL CALCULATIONS
WATER