Abstract
A new modified one-group diffusion scheme for one- and two-dimensional calculations of the gross power distribution in the BWR core is presented. The particularity of the present method is that the fine distribution of the ratio between thermal and fast neutron fluxes within each fuel assembly is estimated analytically. Since this estimation can be performed locally and without requiring knowledge of the fast neutron distribution, the method is quite effective in reducing computing time. Procedures for special treatment at the two-dimensional core-reflector boundaries are also derived from analytical considerations. The results obtained from a series of test calculations indicate that the present method assures an accuracy almost equal to the conventional two-group calculation, and without requiring much more computing time than the conventional one-group calculation. The applicability of the method to three-dimensional calculations is also discussed.
Published Version
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