[en] The paper contains details of PINEX-AR code and its application to the PINEX-2 experiment together with FRAX-2/PINEX-AR studies of the effect of internal fuel pin motion during the course of fast and slow transient overpower accidents in a reactor model. 7 refs
Anon; p. 2030-2039; 1979; p. 2030-2039; American Nuclear Society; La Grange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979