The University of Manchester has an established and growing presence in the fusion space. We are currently a partner of the Fusion Power Centre for Doctoral Training and the lead institute of the new Fusion Engineering CDT. This demonstrates our excellent capabilities in translating from low TRL level research to a position where codes and standards can be developed. We are also part of the...
Nuclear design codes and standards play a critical role in ensuring the safety, reliability, and efficiency of systems, structures, and components in the nuclear industry. Developed by internationally recognized bodies (such as ASME, AFCEN, etc.) based on decades of operational experience and research, with extensive contributions from field experts, these standards reflect proven practices,...
Tritium management is central to the safe and economic operation of future fusion power plants, yet it remains one of the most complex aspects of reactor design. At the component level, accurate prediction of hydrogen isotope behaviour in breeder materials, structural alloys, and plasma-facing components is required to ensure compliance with safety standards on tritium retention, permeation,...
As a pioneer in Chinese fusion research and a key part of China Fusion Energy Company, the Southwestern Institute of Physics (SWIP) is at the forefront of developing vital Codes & Standards (C&S). This presentation shares our experience in establishing key domestic standards (covering vacuum, materials, breeding blankets, and safety) and leading international efforts, including publishing the...
In-Vessel components in fusion nuclear systems have to withstand a very harsh combination of loads and environmental conditions which leads to designs that are significantly more complex and distinct from those of fission components. The ability to accurately predict component performance in in-vessel conditions, factoring in suitable design margins against critical failure mechanisms, is an...
The blankets in Fusion reactor include both shielding blankets and tritium breeding blankets, both of which have been extensively researched at the Southwestern Institute of Physics (SWIP) under the Nuclear Industry Corporation. Based on the absorption of hot helium leak detection technology for shielding blankets, SWIP has published an international standard, ISO 4233: Reactor technology —...
Started from 2022, an ISO standard item was proposed to summarise requirements to the safety systems due to the application of the superconducting technology in magnetic fusion facilities. The initial consideration was to analyse how the radiation safety and new technologies such as the superconducting technology may be cross-affected. To date, it is moving towards the ballot of the final DIS...
As a nuclear technology, fusion energy may be subjected to the stringent regulatory environments such as nuclear (fission) power plants. Software codes and standards need to be developed in acknowledgement of the uncertain regulatory environment, and to meet the Technology Readiness Level (TRL) required to deploy and operate a fusion power plant. Currently, the most mature fusion technologies...
K-DEMO is a conceptual design project led by Korea to demonstrate the feasibility of a fusion power plant, targeting net electricity production, tritium self-sufficiency, and structural integrity under operational and accidental conditions. Its development requires not only advanced technology but also a regulatory framework tailored to fusion-specific hazards, such as tritium management and...
This presentation primarily presents the development of China's fusion standards, as well as the current information and status regarding nuclear safety regulations and standards. It briefly outlines the specific practices of standard - related activities carried out by us based on tasks such as the ITER project, including the current Specialized standards, national standards, and...
In order to advance to the construction and operation of a Fusion Pilot Plant (FPP), numerous engineering and technology advancements are required. In order to de-risk the design and operation of an FPP, as well as to qualify materials and components, a number of test stands have been considered for construction. These include a Fusion Prototypic Neutron Source, a Blanket Test Facility, a...
Tritium breeding blanket is the core component in the future fusion power plants, which is responsible for tritium breeding, neutron shielding and heat extraction. In order to realize these functions, the blanket component usually is designed as a box-structure modular made of steel plates, into which the tritium breeding materials and neutron multiplying materials were filled. To exhaust the...
Codes and standards (C&S) play an important role in the regulatory frameworks for both, radiation protection and nuclear facilities. Currently, internationally different approaches for fusion regulation either already exists or are currently being developed based either the regulatory framework for radiation protection or nuclear facilities. Thereby, the fusion regulatory framework most likely...
UKAEA is committed to the development of codes and standards for the wide-ranging fusion technologies. In this talk, an overview of the UKAEA engagement with codes and standards development organisation such as ASME, BSI and ISO will be presented considering the UK fusion regulatory framework. Also, UKAEA view on key challenges facing the realisation of fusion codes and standards will be...
