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CADDS: computer application to direct digital simulation of transients in PWRs with or without scram. Revision 1

Y.H. Hsii, Charles E. Watson, Nirmala Vasudevan, S.E. Busby, R.L. Trent

Abstract

The CADDS digital computer code is used to analyze reactor transients, with or without scram, in a heterogeneous pressurized water reactor. It solves the time-dependent neutron kinetics equations in conjunction with a thermal-hydraulic solution for an average fuel pin during a reactivity transient. The simulation includes the major feedback mechanism as well as detailed single-phase nucleate boiling, transition, and stable film boiling core heat transfer models. The entire reactor coolant loop, including the pressurizer, is simulated. The steam generator model is included to evaluate the effect of feedwater variations on the steam generator as well as the primary system response.

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Available abstract

Key concepts: Scram, Boiler feedwater, Pressurizer, Nuclear engineering, Pressurized water reactor, Coolant, Thermal hydraulics, Boiler (water heating)