TWO-GROUP, SMALL SOURCE THEORY APPLIED TO AN INFINITE ARRAY OF REACTOR SUPER-LATTICES
Technical Report
·
OSTI ID:4019814
A method of calculating the spatial distribution of the neutron flux in a heterogeneous reactor composed of parallel fuel elements with a complex lattice array by means of a small source theory is discussed. The technique provides for normalizing directly to experimental flux traverses in the uniform array so that the accuracy of calculations of changes in reactivity as the result of changes in the lattice configuration is increased. The necessity of knowing experimental flux traverses within the fuel reglons was eliminated. The formulation of the theory is given together with applications to both simple and complex lattice arrays. (M.C.G.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-15-017743
- OSTI ID:
- 4019814
- Report Number(s):
- HW-63072
- Country of Publication:
- United States
- Language:
- English
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