Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Application of hot channel analysis to KNK-II

Abstract

By means of the codes STAR and TRIBUT, whose principles are shortly described, a statistical uncertainty analysis can be performed. It is shown that in the KMK-II core the two design limits (max. linear power and max. sodium temperature at core outlet) will not be exceeded with high probability. Concerning linear power, we start at a given nominal power distribution and calculate the probability that no pellet exceeds the limit. In this paper, the limit is taken as a parameter in order to compare the codes and to weight 'the influences of different types of uncertainty distribution functions. Additionally, we classify the pellets in the range of high linear poster and determine the probability distribution function of the pellets in excess of a limit of the linear power. Concerning sodium temperature at core outlet, we don't start from the nominal distribution but from an assumed global probability that all the channel temperatures of the considered reactor zone will be below the design limit. However, in order to determine the nominal temperature distribution, there has to be an additional criterion, how to link the individual temperature levels of the subassemblies together. Three criteria have been studied, their influences on the nominal temperature levels of the subassemblies and on the core data are evaluated.

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Reference:

Summary report of a panel meeting held in Karlsruhe, 22-24 November 1973 on the recommendation of the International Working Group on Fast Reactors. 1974. p. 133-142

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--166, pp:163-190