Expansion of the method of correlated temperatures to clad and fuel design analyses

Abstract

In the thermal design of nuclear reactor cores, specified design limits (temperatures and linear power rating) should not be exceeded by the operating values of certain elements (coolant, clad and fuel). However, a certain number of channels or fuel pins could be permitted to exceed the specified limits without affecting the reactor's safety while still allowing reliable operation. An expansion of the method of correlated temperatures, developed for coolant temperature analysis, was performed to enable clad temperature and fuel centerline melting analyses for reactor core reliability studies. Since generation of random numbers is involved, calculational procedures, tailored to designer needs, were developed in order to reduce computational time. The method is applied to a typical LMFBR core and results are presented for various assumed clad and fuel design limits.