Codes, standards and structural integrity are multidisciplinary fields in which UKAEA has a distinguished history of groundbreaking research and innovation, delivering significant economic benefits and enhancing energy security for the UK. After decades of worldwide research and development including recent world records for inertial and magnetic fusion energy, fusion is progressing steadily...
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,...
The approach taken by Rolls-Royce Nuclear to justify the application of advanced manufacturing applied techniques to nuclear plant components, The components are classed to the ASME Section III nuclear design code as Class 1, which are used in the primary circuit and support systems of fission nuclear reactor plants. The manufacturing techniques covered are: Hot Isostatic Pressing (HIP) and...
Lead–lithium (PbLi) eutectic is a cornerstone material for fusion breeding blankets, serving both as a tritium breeder and neutron multiplier. It has emerged as the leading candidate across most liquid blanket concepts: forming the basis of the DCLL, WCLL, and HCLL designs in the EUROfusion DEMO programme; underpinning the WCLL blanket under evaluation in ITER’s Test Blanket Module programme;...
This presentation provides an overview of ITER’s experience in selecting, adapting, or developing mechanical Codes & Standards for the design and construction of Tokamak components such as magnets or Vacuum Vessels and their internal components. Particular attention will be given to aspects unique to fusion, such as Electro-Magnetic loading, cryogenic temperatures, and vacuum environments. The...
An overview of the current development and design concepts of the magnet systems needed to confine plasma in devices under construction and future fusion machines will be presented. Design concepts will include both low and high temperature superconductors. Design criteria and possible codes and standards which can be applied during conception, development and construction of these complex...
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...
One of the largest factors severely limiting the anticipated pace to realize fusion on the grid is the development of a set of basic fusion materials, qualified and validated in expensive irradiation campaigns. Initiated by an international working group, Clean Air Task Force’s “Material Database for Fusion” (MatDB4Fusion) aims to collect all kinds of material properties data which are...
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...
The Japan Society of Mechanical Engineers (JSME) developed a fusion standard for superconducting magnet structure based on ITER design and 1st version was published in 2008. Basic concepts and features of this standard is summarized as follows;
(1) Quality class is equivalent to general structures or general pressure vessels, which are fabricated by the American Society of Mechanical...
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...
The purpose of design codes and standards is to establish national or international standards that consist of a set of rules based on state-of-the-art knowledge, experience, and experimental feedback from facilities. The design and construction of any fusion reactor should make use of appropriate codes and standards to provide quality assurance and control for the structural integrity and...
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...
The development of fusion energy requires robust, harmonised Codes and Standards (C&S) to ensure safety, reliability, and regulatory acceptance. Kyoto Fusioneering (KF) has extensive experience applying ASME, JSME, RCC-MRx, and CSA frameworks to real projects, including hydrogen isotope permeation sensors (TRI-PRISM) and the UNITY-2 tritium facility. KF actively contributes to shaping future...
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...
In the fission industry, nuclear installations are designed and constructed following established Codes and Standards (C&S), developed over decades based on operational feedback and regulatory requirements. In contrast, fusion facilities lack a harmonized regulatory framework and their safety hazards are different from those of fission plants. Additionally, while mission-critical components -...
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...
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...
In March 2023, the U.S. Nuclear Regulatory Commission (NRC) unanimously agreed to regulate fusion energy facilities under the byproduct materials framework of 10 CFR 30—commonly applied to particle accelerators and medical irradiation systems—rather than the 10 CFR 50/52 framework for fission reactors. This approach mirrors that of the U.K., where fusion facilities are overseen by the Health...
This presentation examines strategic approaches to fusion codes and standards development, emphasizing three key principles: leveraging existing commercial industry standards, allowing adequate operational experience and design standardization prior to establishing fusion-specific requirements, and assessing the most efficient and appropriate regulatory applications for codes and standards....
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...
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...
A Machine Protection System (MPS) is a fundamental component of any fusion facility, serving as the first line of defence for safeguarding essential equipment and ensuring operational integrity under both normal and off-normal conditions. As fusion devices progress toward higher power, increased complexity, and extended operational regimes, the MPS assumes a central role within the overall...
Liberty Fusion is a New Mexico–based startup pursuing Plasma-Jet Magneto-Inertial Fusion (PJMIF), a cost-focused path to commercial fusion energy. Our mission is to achieve sub-$50/MWh electricity through scalable plasma gun–driven systems. In parallel with technical milestones (high-fidelity simulations, prototype plasma gun design, and relocation of the Plasma Liner Experiment from Los...
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,...
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...
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...
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 —...
