Thermal-hydraulic aspects of CAREM reactor

The CAREM nuclear power plant design is based on a light water integrated reactor. The whole high-energy primary system, core, steam generators, primary coolant and steam dome, is contained inside a single pressure vessel. 

Self-pressurisation of the primary system in the steam dome is the result of the liquid-vapour equilibrium. The large volume of the integral pressuriser also contributes to the damping of eventual pressure perturbations. Due to self-pressurisation, bulk temperature at core outlet corresponds to saturation temperature at primary pressure. Heaters and sprinkles typical of conventional PWR s are thus eliminated. 

The thermal hydraulic behavior of the CAREM reactor was study using generic numerical codes. Several transients and accidental situations were analyzed. 

The dynamic analysis of the plant during operational transients and accidents has been performed mainly with RETRAN-02 code [1]. 

Power evolution during a temporary decrease of the power reference value. 

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DELMASTRO, D.F., Thermal-hydraulic aspects of CAREM reactor , IAEA TCM on Natural Circulation Data and Methods for Innovative Nuclear Power Plant Design, Vienna, 18-21 July 2000. 

An overview of the thermal hydraulic aspects of CAREM reactor was presented. The analytical dynamical studies and experimental facility, studies and results were briefly presented. 

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