Conveners
Topic I: Session 1: Chaired by Richard Kamendje
- Qiang Qi (Institute of Plasma Physics, Chinese Academy of Sciences)
- Lei Chen (Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP))
- Kazunari katayama (Kyushu University)
- Gabriele Ferrero (Politecnico di Torino)
- Luciano Giancarli (ITER Organisation)
Topic I: Session 2: Chaired by Alessandro Spagnuolo
- Gaetano Bongiovi (Universitร degli Studi di Palermo)
- Guangming Zhou (Karlsruhe Institute of Technology (KIT))
- Davide Pettinari (Politecnico di Torino)
- Hiroyasu Tanigawa (Japan Atomic Energy Agency)
- David Pickersgill (United Kingdom Atomic Energy Authority)
Topic I: Session 3: Chaired by Songlin Liu
- Christopher Harrington (United Kingdom Atomic Energy Authority)
- Luigi Candido (Kyoto Fusioneering Ltd)
- Yi-Hyun PARK (Korea Institute of Fusion Energy)
- Tommi Lyytinen (VTT Technical Research Center of Finland)
- Helen Brooks (UKAEA)
In ITER, two dedicated equatorial ports are allocated for the TBM (Test Blanket Module) Program in order to allow the operation and testing of Test Blanket Systems (TBS) that are relevant mock-ups of tritium breeding blankets systems for fusion power reactors, using operation parameters typical for power reactors. The ITER baseline 2024 foresees two phases, DT-1 and DT-2. During DT-1, the plan...
The water-cooled ceramic breeder (WCCB) blanket has been developing as a near-term solid blanket candidate for the Chinese Fusion Engineering Testing Reactor (CFETR). Meanwhile, the supercritical CO2 cOoled Lithium-Lead (COOL) blanket has been proposed as an advanced candidate in recent years. This presentation reports the overall design and performance analysis for both WCCB and COOL...
In D-T fusion reactors, tritium self-sufficiency is one of the key factors for maintaining steady-state operation. The key factors of tritium breeding materials are effective tritium breeding and stability of performance under long-term service. In terms of tritium breeding, a high lithium atom density is essential to produce substantial amounts of tritium, and good tritium release properties...
The outer fuel cycle (OFC) of a fusion power plant (FPP) is a fundamental component that allows retrieving the bred tritium to permit D-T plasma operations. Moreover, this system plays a fundamental role for the safety of workers and population, acting as a physical barrier that delimits the tritiated circuit, and extracts tritium from the system, thereby diminishing the tritium inventory both...
From the viewpoint of fuel control and tritium safety in a DT fusion reactor, it is important to correctly understand the tritium behavior in the blanket system. Previous studies have shown that the tritium generated by the nuclear reaction of lithium and neutron is released as both of HT and HTO from solid breeder materials such as Li2TiO3 and Li4SiO4. The HT / HTO ratio depends on the kind...
The water-cooled solid breeder concept has been adopted as the concept of tritium breeding blanket for Japanese DEMOnstration fusion reactor (JA DEMO). The coolant water conditions are similar to those of pressurized water reactor, with the temperature of 290 โ 325ยฐC and an operation pressure of 15.5 MPa. The design has evolved to simultaneously meet the requirements of structural integrity...
The design of the breeding blanket (BB) system represents one of the biggest challenges towards the accomplishment of the conceptual design of the DEMO fusion reactor, due to its pivotal role in the machine operations. In this regard, novel BB concepts have been recently emerging in Europe with the aim of developing BB configurations capable of surmounting the major criticalities emerged so...
Within the EUROfusion DEMO programme, the Helium Cooled Pebble Bed (HCPB) breeding blanket is being developed as a reactor-relevant breeding blanket for the European DEMO. The reference design of this concept employs pressurized helium (8 MPa) as the coolant, a lithium-ceramic pebble bed as the tritium breeder, and beryllide blocks (beryllium-based alloys) as neutron multipliers. Tritium...
The choice of breeding blanket configuration represents one of the most critical design aspects for the viability of future D-T fusion power plants. POLITO and Eni have investigated and compared different breeding blanket concepts by evaluating their neutronic performance under consistent reactor boundary conditions. The objective is to provide a systematic assessment of the impact of blanket...
Many public and privately funded fusion reactors are due to begin operation around the middle of the 21st century, the vast majority of which will rely on a deuterium and tritium fuel cycle, with a lithium-containing breeder blanket responsible for providing a sustainable tritium supply. The tritium consumption of large (DEMO-scale) devices will be in the order of 100kg per full power year,...
The breeder blanket for the STEP Prototype Powerplant (SPP) must provide high performance breeding for a spherical tokamak without inboard breeding, materials and coolant compatible with a 600 ยฐC outlet temperature for net power confidence, and a system deliverable on the targeted timescales of the STEP programme. Following a comprehensive assessment of all breeder, coolant, and structural...
The breeding blanket is one of the key components for the realization of fusion energy. It plays multiple roles, including tritium breeding for fuel self-sufficiency, heat extraction for power generation, and neutron and gamma-ray shielding for the protection of other reactor components. Reduced Activation Ferritic/Martensitic (RAFM) steel is the primary candidate for the structural material,...
Fusion breeding blankets must fulfil multiple competing objectives: maximising the extraction of both tritium and heat, minimising damaging irradiation to less resilient components (such as magnets), whilst maintaining temperatures, stresses and radiation doses below safe operational limits. To reduce costs and timescales, exploring those trade-offs efficiently is desirable, mandating an...
The development of next-generation stellarators is rapidly advancing, driven by recent progress in stellarator optimization that enables enhanced MHD stability and reduced turbulence [1]. Alongside public research initiatives, private companies are also pursuing pilot power plant concepts based on these designs. For a fusion reactor to operate sustainably, it must include a breeding blanket...
