The paper gives an analysis of the current state of the RBMK safety evaluation in accidents initiated by partial ruptures of the delivery part of the circulating loop. It appears from this analysis that applicability and uncertainty of the international code RELAP for RBMK safety analysis could not be determined up to the present. At the same time it is shown in the paper that fuel rod cladding temperature can reach the acceptability criterion in the accidents. As a result it has been concluded that bases of the next stage of the RBMK safety analysis would be creation of a code oriented to the special features of a reactor RBMK.

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