22.08.2015   Natural circulation data and methods for advanced water cooled nuclear power plant designs

NUMERICAL STUDIES

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].

As an example, Figures 2 and 3 show the power and pressures evolution for a 5% decrease in the reference value during 150 seconds. In this case a classical controller was used.

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FIG. 1. Primary system cool ant natural circulation.

120

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time (s)

FIG. 2. Power evolution during a temporary decrease of the power reference value.

Pressure

(bar)

 

time (s)

 

FIG. 3. Pressures evolution during a temporary decrease of the power reference value.

 

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2. EXPERIMENTAL STUDIES

A High Pressure Natural Convection Loop (CAPCN) was constructed and operated to produce data in order to verify the thermal hydraulic tools used to design CAREM reactor, mainly its dynamical response. This is accomplished by the validation of the calculation procedures and codes for the rig working in states that are very close to the operating states of CAREM reactor.