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Simplified thermohydraulic criteria for a comparison of the accidental behaviour of GEN IV nuclear reactors and of PWRs

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Academic year: 2021

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Figure

Figure 1. VHTR core and vessel system arrangement [1]
Figure  2.  arrangement of the GFR primary circuit components (RHP: high pressure DHR loops;
Figure 3. Primary system arrangement for ASTRID  .
Figure 4: Sketch of the primary vessel of a 1300 MWe PWR [5]
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