Page 31 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

6 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

China and India, design work progresses with follow-up prototypes in the line of the
CEFR in China and the PFBR in India. China is also embracing the lead technology in
the so-called CLEAR reactor line. The main design efforts in Europe are
illustrated below.

1.5.1 ASTRID (Fig. 1.2)

Fig. 1.2 ASTRID primary
circuit internals (©CEA).

Full name: Advanced Sodium Technology Reactor for Industrial
Demonstration
Designer: ASTRID Consortium (CEA, Framatome, JAEA, and MFBR)
Reactor type: Sodium fast reactor
Electric capacity: 600MW(e)
Thermal capacity: 1500MW(th)
Coolant: Sodium
System pressure: <5atm
System temperature: 400°C/550°C (core inlet/outlet)
No. of safety trains: 6 trains
Emergency safety No injection safety systems needed
systems:
Residual heat removal Three DHR systems (two passive+two active DRACS and two
systems: active RVACS)
Design status: Basic design
New/distinguishing Pool type, sodium cooled, low-void effect, Brayton PCS, and
features: passive DHR