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1. Introduction<br />

In the EADF design [1,2], the primary-coolant flow is assured by natural convection and<br />

enhanced by a particular system of cover gas injection into the bottom part of the riser. The aim of this<br />

work is to present a simple model that has been recently developed at ENEA Casaccia to preliminarily<br />

investigate the capability that the primary-coolant natural convection has to mitigate typical core<br />

transients in ADS. The model, that allows to quickly evaluate the primary-coolant velocity variation<br />

induced by the natural convection during the core transients, has been already implemented in the<br />

Tieste-Minosse code [3,4] recently developed at ENEA to preliminarily investigate core transients in<br />

solid fuelled ADS [5]. Results obtained by taking into account the primary-coolant velocity variations<br />

evaluated by means of the simple natural convection model are also presented and compared with the<br />

corresponding transient trends obtained by considering a constant primary-coolant flow. In particular,<br />

the present paper results concern transients induced by: 1) the proton beam interruption [6-9] or short<br />

duration beam trips [5,10]; 2) the proton beam jumps [5,11,12,13]; 3) the loss of the primary-flow due<br />

to the failure of the active system of convection enhancement.<br />

2. The simple model<br />

We face the subject of the natural convection process, in the attempt to derive a simplified model<br />

to be easily used in core dynamics codes for solid fuelled ADS. We aim to obtain a preliminary<br />

evaluation of the natural convection impact on liquid metal cooled ADS dynamics. In order to make<br />

this quick evaluation, we assume the possibility of reducing a three-dimensional configuration (the<br />

actual plant) into a one-dimensional model. Practically, this assumption leads to neglect the recirculation<br />

phenomena into the vessel pool.<br />

Moreover, we will take into account the heat exchange from the fuel to the coolant into the core<br />

and from the primary to the secondary loop coolant into the heat exchangers, but we will neglect the<br />

heat exchange between the primary coolant and the loop walls. Finally, we will consider the coolant<br />

movement, but we will neglect the heat conduction along the coolant.<br />

To look for the hydraulic solutions of a single-phase fluid, flowing in a supposed onedimensional<br />

loop, in the following we will indicate with:<br />

ν the mean velocity of the primary-coolant<br />

ρ the primary-coolant density<br />

σ the generic section area of the primary loop<br />

Q V<br />

the volume flow rate≡ ρ σ<br />

Q m<br />

the mass flow rate ≡ Q σ = ρσ ν<br />

V<br />

G the specific flow rate ≡ Q m<br />

/ σ.<br />

As a consequence of the mass conservation, assuming a generic volume V inside two normal<br />

sections of a stream-tube, we can write the following equation of continuity:<br />

∂<br />

∫ ρ ( t<br />

∂ t<br />

)<br />

V<br />

dV<br />

=<br />

Q<br />

m<br />

− Q ′<br />

m<br />

(1)<br />

510

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