Neutron diffusion in graphite poisoned with 1/v and non-1/v absorbers
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), Vol. 81:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
NEUTRONS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
REACTOR CORES
NEUTRON ABSORBERS
CADMIUM
COMPARATIVE EVALUATIONS
CROSS SECTIONS
DIFFUSION
ENERGY ABSORPTION
ENERGY SPECTRA
GADOLINIUM
GRAPHITE
KERNELS
MATHEMATICAL MODELS
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR POISONS
PARAMETRIC ANALYSIS
POISONING
SAMARIUM
SCATTERING
ABSORPTION
BARYONS
CARBON
DIFFERENTIAL EQUATIONS
ELEMENTAL MINERALS
ELEMENTARY PARTICLES
ELEMENTS
EQUATIONS
FERMIONS
HADRONS
MATERIALS
METALS
MINERALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NONMETALS
NUCLEONS
RADIATION FLUX
RADIATION TRANSPORT
RARE EARTHS
REACTOR COMPONENTS
REACTOR MATERIALS
SPECTRA
TRANSPORT THEORY
220400* - Nuclear Reactor Technology- Control Systems