Work

Advancements in breeding blanket: Key to realizing spherical tokamak-based nuclear fusion power

Year: 2025

Type: article

Abstract: This review critically assesses conceptualised breeding blanket (BB) focusing on its potential for implementation in spherical tokamak (ST) demonstration (DEMO) reactors. Existing studies highlighted that configuration design, material selection and tritium extraction technologies influence neutronics, thermal-hydraulics, structural and integration performance of BB concepts developed for conventional tokamaks. Currently, there is growing interest for liquid metal and hybrid breeders primarily driven by their tritium breeding ratio (TBR) of up to 1.24 and heat transfer performance which allows for a helium coolant outlet temperature of approximately 520 °C from fusion reactor. The performance of ST-DEMO BB can be optimised through considerations such as compact geometry, heat removal under high power density, TBR, use of radiation-resistant structural materials, mitigation of magneto-hydrodynamics (MHD) effect, seamless system integration and maintainability. The strategic implementation of maturing BB concepts such as helium-cooled pebble bed and molten salt breeder blanket can contribute to achieving the goal of realising self-sustaining, safe and commercially relevant fusion energy from ST DEMO reactors. Advancing BB technology for fusion DEMO reactor requires addressing challenges such as limited information under transient occurrences relating to coolant control, MHD effect and structural integrity which determine its performance and readiness at system-integrated level. Future research should focus on optimising BB designs to ST constraints such as tight radial build, high heat flux and power density using robust irradiation-tolerant materials and emerging test infrastructures.

Source: Results in Engineering

DOI: 10.1016/j.rineng.2025.108406

Authors: Damilola Olumuyiwa Olatujoye, Davannendran Chandran, Ainul Akmar Mokhtar

Institution: Universiti Teknologi Petronas

Language: English

Topic: Fusion materials and technologies

Subfield: Materials Chemistry

Field: Materials Science

Domain: Physical Sciences

SDG: Affordable and clean energy

Open Access status: gold

Estimated APC paid: $1,940