Onedimensional homogenized reactor with natural uranium and with flattened specific output
Rostislav Zezula (1969)
Aplikace matematiky
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Rostislav Zezula (1969)
Aplikace matematiky
Similarity:
Rostislav Zezula (1969)
Aplikace matematiky
Similarity:
The main results of this paper, in which the problem of determination of the fuel concentration distribution inducing a prescribed thermal neutron flux in the homogenized critical reactor core with given outer reflector boundary is investigated (in the two-groups diffusion approximation), are stated in the theorems 1 and 2. In theorem 1 sufficient conditions are given for the existence of a oneparametrical family of thermal neutron fluxes induced by the Goertzel’s type fuel concentration...
B. Urgošík (1979)
Acta Universitatis Carolinae. Mathematica et Physica
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