Neutron diffusion in graphite poisoned with 1/v and non-1/v absorbers
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6834995
Neutron diffusion in graphite containing 1/v and non-1/v absorbers has been studied in the diffusion theory approximation using a multigroup (30-group) approach and the neutron scattering kernel proposed earlier by the authors. It is observed that, in this case as in the case of water investigated earlier, the behavior of neutrons in graphite poisoned with gadolinium is different from that in graphite poisoned with samarium or cadmium. To explain the reason for this difference, a hypothetical model for the energy variation of the absorption cross section has been constructed that closely resembles samarium in one limit and goes over to gadolinium in the other. The effect of varying the concentration of non-1/v absorbers on the flux of sub-Bragg and epicold neutrons has been studied for this model, and some interesting results are obtained.
- Research Organization:
- University of Delhi, Department of Physics and Astrophysics Delhi-110007
- OSTI ID:
- 6834995
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 81:1; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ABSORPTION
BARYONS
CADMIUM
CARBON
COMPARATIVE EVALUATIONS
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIFFUSION
ELEMENTAL MINERALS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY ABSORPTION
ENERGY SPECTRA
EQUATIONS
FERMIONS
GADOLINIUM
GRAPHITE
HADRONS
KERNELS
MATERIALS
MATHEMATICAL MODELS
METALS
MINERALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ABSORBERS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NONMETALS
NUCLEAR POISONS
NUCLEONS
PARAMETRIC ANALYSIS
POISONING
RADIATION FLUX
RADIATION TRANSPORT
RARE EARTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
SAMARIUM
SCATTERING
SPECTRA
TRANSPORT THEORY
220400* -- Nuclear Reactor Technology-- Control Systems
ABSORPTION
BARYONS
CADMIUM
CARBON
COMPARATIVE EVALUATIONS
CROSS SECTIONS
DIFFERENTIAL EQUATIONS
DIFFUSION
ELEMENTAL MINERALS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY ABSORPTION
ENERGY SPECTRA
EQUATIONS
FERMIONS
GADOLINIUM
GRAPHITE
HADRONS
KERNELS
MATERIALS
MATHEMATICAL MODELS
METALS
MINERALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ABSORBERS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NONMETALS
NUCLEAR POISONS
NUCLEONS
PARAMETRIC ANALYSIS
POISONING
RADIATION FLUX
RADIATION TRANSPORT
RARE EARTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
SAMARIUM
SCATTERING
SPECTRA
TRANSPORT THEORY