A semianalytic solution of the monoenergetic transport equation in cylindrical geometry and the derivation of fluxes from singular sources
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5004172
The neutron flux /PHI/ (r,..cap omega..) at position r in the direction of unit vector ..cap omega.. is expanded as a series of the form with P /SUP M/ /SUB l/ (costheta),the associated Legendre polynomial of order l,m. Variables theta and /theta/ are the angles defining ..cap omega.. and N, an arbitrary odd number. Equations obtained for /phi/ /SUB lm/ (r) have solutions involving linear binations combinations of Bessel functions of the first and second kind. Expressions for the fluxes from point, line, and plane sources are found using a Green's function technique.
- Research Organization:
- United Kingdom Atomic Energy Authority, E276 UKAEA Risley, Warrington, Cheshire
- OSTI ID:
- 5004172
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 85:1; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANALYTICAL SOLUTION
CALCULATION METHODS
CONFIGURATION
CYLINDRICAL CONFIGURATION
EQUATIONS
FUNCTIONS
GREEN FUNCTION
LEGENDRE POLYNOMIALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
POLYNOMIALS
RADIATION FLUX
RADIATION TRANSPORT
TRANSPORT THEORY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANALYTICAL SOLUTION
CALCULATION METHODS
CONFIGURATION
CYLINDRICAL CONFIGURATION
EQUATIONS
FUNCTIONS
GREEN FUNCTION
LEGENDRE POLYNOMIALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
POLYNOMIALS
RADIATION FLUX
RADIATION TRANSPORT
TRANSPORT THEORY