The Chinese Fusion Engineering Testing Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China. It will be operated in two phases. The fusion power is up to 200MW for Phase-I and will be over 1GW for Phase-II. The water cooled breeder blanket (WCCB) is one of three candidates.
The WCCB modules surrounding the plasma and its primary heat transfer...
In the framework of the EUROfusion’s Power Plant Physics and Technology, the Working Package Breeding Blanket aims at investigating 4 different Breeding Blanket (BB) concepts for a EU Demonstration Fusion Reactor Concept (DEMO). One of these concepts is the Helium Cooled Pebble Bed BB, which is based on the use of pebble beds of lithium ternary ceramic compounds and beryllium (or beryllides)...
The solid blanket is a candidate tritium breeding blanket concept for Chinese Fusion Engineering Test Reactor (CFETR), and the thermal and mechanical characterization of the ceramic pebble beds are vital for researchers to know for a reliable solid blanket design. Some related numerical and experimental studies were conducted at University of Science and Technology of China and China Academy...
Design of the Water Cooled Ceramic Breeder (WCCB) blanket includes beryllium multiplier layers. At elevated temperature, beryllium reacts with steam in an exothermic reaction producing beryllium oxide and hydrogen. Such situation may occur in WCCB in case of the rupture of one of the cooling pipes in the blanket module. This process occurs locally in a complex 3D geometry of the blanket...
Lithium orthosilicate (Li4SiO4), in the form of ceramic pebble, is one of the most promising tritium breeder materials for fusion reactor blankets. Particularly, Li4SiO4 has been selected as the preferred breeder material for Chinese HCCB-TBM . For efficient extraction and recovery of bred tritium in the breeding blankets, it is important to have a thorough understanding of the mechanisms of...
In the frame of the EU DEMO design and analysis activities, the development of a system-level thermal-hydraulic model (the GEneral Tokamak THErmal-hydraulic Model – GETTHEM) of the EU DEMO tokamak has been recently launched at Politecnico di Torino, with the aim of building a tool which would allow a reasonably fast simulation of the entire power conversion system. The GETTHEM development...
