Page 37 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

12 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

the in-pile test sections and the beam tube, fuel handling is done from underneath the
core. Two in-vessel fuel-handling machines fulfill this function. The primary, second-
ary, and tertiary cooling systems have been designed to evacuate a maximum core
power of 110MW(th). The primary cooling system consists of two pumps and four
primary heat exchangers. The secondary cooling system is a water-cooling system,
providing pressurized water to the primary heat exchangers. The tertiary cooling
system is an air-cooling system.

1.5.3.3 Description of the safety concept

In case of loss of the primary flow, the beam must be shut off in subcritical case and the
safety rods inserted in critical mode. The primary, secondary, and tertiary cooling sys-
tems have been designed to remove the decay heat using natural convection. Ultimate
decay heat removal is achieved by the reactor vessel cooling system, also by natural
convection. In the unlikely event of a reactor vessel breach, the reactor pit will fulfill
the function of secondary containment to keep the lead-bismuth in place.

1.5.3.4 Deployment status and planned schedule
The implementation of MYRRHA follows a phased approach. In phase 1 (2016–24), a
100MeV particle accelerator will be constructed together with stations for the produc-
tion of radioisotopes and material research. Hence, in 2024, a first R&D facility will
become available. In parallel, the preconstruction engineering and design of the reac-
tor will continue and conclude. The prelicensing phase will conclude, and the licens-
ing phase will start.
In phase 2 (2025–30), the 600MeV particle accelerator and the reactor will be
developed and constructed. The end of the construction phase is foreseen by 2030
and end of commissioning by 2033.

1.5.4 SEALER (Fig. 1.5)

Full name: Swedish Advanced Lead-cooled Reactor
Designer: LeadCold Reactors
Reactor type: Pool
Electric capacity: 3MW(e)
Thermal capacity: 8MW(th)
Coolant: Lead
System pressure: 0.1MPa
System temperature: 390°C/430°C (core inlet/outlet)
No. of safety trains: 2
Emergency safety systems: Passive
Residual heat removal systems: Passive
Design status: Conceptual design
New/distinguishing features: Full decay heat removal by radiation through vessel
High-density shutdown rod absorber
No fuel reload during 30 years of operational life