[en] The prestressed concrete reactor vessel (PCRV) has thus far been applied for nuclear reactor containments involving steady-state loading. This paper, on the other hand, considers the PCRV for the LMFBR containment which must sustain dynamic effects stemming from the Hypothetical Core Disruptive Accident (HCDA). To perform a feasibility study of such a PCRV, a specialized formulation for transient analysis of such structures was developed. The analytical model of a PCRV is represented in a finite element computer code involving an explicit time-integration procedure. The formulation is particularized for the axisymmetric geometry and includes simulations of tensile cracking of concrete, reinforcement and prestressing capability. The code is applied to the analysis of a PCRV in a possible LMFBR configuration. The code provides a useful tool for evaluating the effect of reinforcement and prestressing on crack propatation. By means of the code, the design parameters can be varied to improve and optimize the PCRV configuration. (Auth.)