A semianalytic solution of the monoenergetic transport equation in cylindrical geometry and the derivation of fluxes from singular sources

Journal Article · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Sci. Eng.; (United States)

OSTI ID:6705696

Fletcher, J K

The neutron flux (r,..cap omega..) at position r in the direction of unit vector ..cap omega.. is expanded as a series of the form (r,..cap omega..) = /SUP N/ ..sigma../sub 0/ (21 + 1) /SUP l/ ..sigma../sub 0/ /PSI/lm(r)P /SUP m/ /SUB l/ (cos/PHI/)cos(m) with P /SUP m/ /SUB l/ (cos/PHI/), the associated Legendre polynomial of order l,m. Variables /PHI/ and are the angles defining ..cap omega.. and N, an arbitrary odd number. Equations obtained for /PSI/..mu..(r) have solutions involving linear 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, Risley, Warrington, Cheshire
• OSTI ID: 6705696
• 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

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ANALYTICAL SOLUTION
BESSEL FUNCTIONS
CALCULATION METHODS
CYLINDERS
FUNCTIONS
KINETICS
LEGENDRE POLYNOMIALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON TRANSPORT
PARTICLE SOURCES
POINT SOURCES
POLYNOMIALS
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
REACTOR KINETICS
SERIES EXPANSION