Ricerc@Sapienza

In the Water-Cooled Lithium Lead (WCLL) blanket, a critical problem faced by the design is to ensure that the breeding zone (BZ) is properly cooled by the refrigeration system to keep the structural materials under the maximum allowed temperature by the design criteria. CFD simulations are performed using ANSYS CFX to assess the cooling system performances accounting for the magnetic field effect in the sub-channel closest to the first wall (FW). Here, intense buoyancy forces (Gr = 10^10) interact with the pressure-driven flow (Re = 10^3) in a MHD mixed convection regime.

In the Water-Cooled Lithium Lead (WCLL) blanket, the eutectic alloy lithium-lead (PbLi) is used as tritium breeder and carrier, neutron multiplier and heat transfer medium. The liquid metal is distributed to and collected from the breeding zone through a compact poloidal manifold composed of two co-axial rectangular channels. The external channel, tasked with distribution, and the internal one, assigned to the collection, are co-flowing and share an electrically conductive wall (c_w=0.1).

The Breeding Blanket is a fundamental component of a nuclear fusion reactor and the Water-Cooled Lead Lithium (WCLL) blanket is one of the possible solutions proposed. In this concept, liquid lithium-lead eutectic alloy (PbLi) serves as tritium breeder, tritium carrier and neutron multiplier. The liquid metal is distributed within the breeding zone by two co-axial rectangular channels and, interacting with the reactor magnetic field, leads to the arising of MagnetoHydroDynamic (MHD) effects.

The Water-Cooled Lithium Lead breeding blanket is a candidate option for the realization of European DEMO power plant. One of the main functions of the breeding blanket is to recover the thermal power from the first wall and the breeding zone and to drive it to the Primary Heat Transfer System. Moreover, due to the DEMO pulsed operation, an Energy Storage System is foreseen in order to ensure thermal energy availability and reduce cycling loading during dwell time.

In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water Cooled Lithium Lead Breeding Blanket, which is a candidate option for the European DEMO nuclear fusion reactor.

Purpose of the present study is the exergy analysis of EU DEMO pulsed fusion power plant considering the Primary Heat Transfer Systems, the Intermediate Heat Transfer System (IHTS) including the Energy Storage System (ESS) as a first option to ensure the continuity of electric power released to the grid. A second option here considered is a methane fired auxiliary boiler replacing the ESS. The Power Conversion System (PCS) performance is evaluated as well in the overall balance.

The way to arrive at a licensing phase for a nuclear fusion installation is not straightforward mainly because of the lack of operating experience and of dedicated nuclear regulations. In fact, only small/medium experimental facilities exist with limited licensing processes and only one large experiment, ITER, has obtained a construction license. Therefore, the safety assessment and the preparation of the preliminary safety report is almost a first of a kind for DEMO.

Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling tubes in the breeding zone, and on lithium lead flowing in radial-poloidal direction. This design choice is driven by the rationale to have a modular design, where a basic geometry is repeated along the poloidal direction.

Conceptual activities on the DEMO fusion power plant design are progressing in Europe under the lead of the EUROfusion Consortium. According to the current EU DEMO plant design, the Primary Heat Transfer System (PHTS) transfers heat from the nuclear heat sources, i.e. breeding blanket, divertor and (optionally) vacuum vessel, to the Power Conversion System (PCS) responsible for generating electric energy. To mitigate issues related to the pulsed DEMO operation, adding the Energy Storage System (ESS) filled with molten salt, between the PHTS and PCS, has been proposed.

ENEA CR Brasimone has developed the new design of the Water Cooled Lithium Lead Breeding Blanket(WCLL BB). In the new design Breeding Zone (BZ) water coolant flows in radial-toroidal direction, andPbLi flows in radial-poloidal direction; a gap between the Back Plate (BP) and the BZ constitutes the PbLiinlet manifold. The paper presents the CFD analysis of the WCLL BB PbLi inlet manifold, performed byANSYS CFX-15 code. The objective of the analysis is to investigate the PbLi flow paths in the manifoldregion and to optimize the mass flow rate distribution in the BZ of the module.