Some dynamic A-n, S-2n analytic calculations
Journal Article
·
· Sov. At. Energy (Engl. Transl.); (United States)
A-n, S-2n dynamic equations in neutron transport theory are given an analytic solution, suitable for numerical safety code validation. Some numerical results are presented for plane geometry with periodic boundary conditions, within the monokinetic isotropic scattering case. They turn out to be very interesting and physically well interpretable and seem to give a deep insight into the transport effects connected with the finite velocity space migration of localized neutron signals. Balance equations are solved by means of a space Helmholtz series expansion connected to a time-variable Laplace transformation technique. The equations that are to be solved for the considered slab geometry, although perfectly equivalent to S-2n equations, are actually the ones corresponding to the typical second-order A-n model. The given fully analytic solution can be used to yield standard reference results for peculiar space transients, against which any numerical safety code exploiting the same discrete ordinate model can be validated.
- Research Organization:
- Politecnico di Torino (Italy)
- OSTI ID:
- 5122072
- Journal Information:
- Sov. At. Energy (Engl. Transl.); (United States), Journal Name: Sov. At. Energy (Engl. Transl.); (United States) Vol. 62:5; ISSN SATEA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANALYTICAL SOLUTION
BENCHMARKS
BOUNDARY CONDITIONS
DIFFERENTIAL EQUATIONS
DISCRETE ORDINATE METHOD
EQUATIONS
HELMHOLTZ THEOREM
INTEGRAL TRANSFORMATIONS
LAPLACE TRANSFORMATION
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
POWER REACTORS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR SAFETY
REACTORS
SAFETY
SAFETY STANDARDS
SCATTERING
SERIES EXPANSION
SPACE-TIME
STANDARDS
TESTING
TIME DEPENDENCE
TRANSFORMATIONS
TRANSPORT THEORY
VALIDATION
220900* -- Nuclear Reactor Technology-- Reactor Safety
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANALYTICAL SOLUTION
BENCHMARKS
BOUNDARY CONDITIONS
DIFFERENTIAL EQUATIONS
DISCRETE ORDINATE METHOD
EQUATIONS
HELMHOLTZ THEOREM
INTEGRAL TRANSFORMATIONS
LAPLACE TRANSFORMATION
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
POWER REACTORS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR SAFETY
REACTORS
SAFETY
SAFETY STANDARDS
SCATTERING
SERIES EXPANSION
SPACE-TIME
STANDARDS
TESTING
TIME DEPENDENCE
TRANSFORMATIONS
TRANSPORT THEORY
VALIDATION