Analysis of temperature fields and deformations in fast reactor core

Deformations of the fuel and breeding assemblies of a sodium cooled fast reactor include swelling of the assembly structural material and radiation creep. The swelling and creep depend on the fast neutron dose and on temperature. Code SANDRA (Structural Analysis of LMFBR Ducts during Reactor Operation) in language PL/I allows modelling long-term reactor operation and predicting deformations and power effects of the core fuel assembly system. The code is a system of independent program units linked with the master program. Code SANDRA joins up to calculations of temperature fields in the reactor using code SUPERED. Two examples are given of calculating deformations of power reactor fuel assemblies. (H.S.)