A simple model for the calculation of the sodium-voiding effect on neutron leakages in a fast reactor lattice. I. Formalism

Journal Article · Sun Jan 01 04:00:00 EST 1984 · Nucl. Sci. Eng.; (United States)

OSTI ID:7062954

Benoist, P

A simple formalism, which can be introduced into routine analyses, is presented for the calculation of the effect of sodium voiding on neutron leakages in a fast reactor lattice. The diffusion coefficients in plane or in two-dimensional lattices are calculated following a method that is very analogous to the method proposed earlier by the author for the treatment of thermal reactors. The two situations, sodium present and sodium voided, are calculated with the same approximations. It is known that it is impossible in the situation where the sodium is voided to calculate buckling-independent diffusion coefficients, for they diverge. These coefficients are hence calculated in both situations at the lowest order of the expansion in terms of the buckling, which introduces a logarithmic term. The calculation is performed in the actual geometry of the lattice without cylindricalizing the cell.

• Research Organization: Centre d'Etudes Nucleaires de Saclay Departement des Etudes Mecaniques et Thermiques
• OSTI ID: 7062954
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 86:1; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALKALI METALS
BREEDER REACTORS
BUCKLING
DIFFUSION
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GEOMETRY
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MATHEMATICS
METALS
NEUTRON LEAKAGE
REACTIVITY COEFFICIENTS
REACTOR KINETICS
REACTOR LATTICES
REACTORS
SODIUM
THERMAL REACTORS
TWO-DIMENSIONAL CALCULATIONS
VOID COEFFICIENT