Nuclear fusion energy is emerging as one of the most promising solutions for generating clean and sustainable electricity. The ITER project (International Thermonuclear Experimental Reactor), currently under construction in Cadarache, France, is the world's largest nuclear fusion experiment and seeks to demonstrate the scientific and technological viability of this energy source. To achieve this, the materials that make up the reactor must withstand extreme conditions: cryogenic temperatures, neutron irradiation, intense magnetic fields, and thermal cycles.
Advanced epoxy matrix and fiberglass composite materials were selected for the electrical insulation of the ITER reactor's thermal shield due to their excellent mechanical behavior and dielectric properties under extreme conditions. The initial standard composite did not meet the requirements after irradiation, which led to a search for alternatives. Based on studies by CERN, three options were evaluated: a high-cost advanced material (A), another with random fibers and lower performance (B), and a customized variant without boron and longitudinal fibers that met all requirements (C). This paper describes the collaboration between ITER, CERN, and Applus+ Laboratories to develop and validate post-irradiation cryogenic (77 K) testing protocols, solving challenges such as slippage in the jaws.
ITER reactor materials must withstand extreme environments: cryogenic temperatures, neutron irradiation, and electromagnetic fields, while maintaining mechanical properties and electrical insulation. To reproduce these conditions in the laboratory, tests require:
Neutron irradiation alters the polymer matrix, increasing rigidity and reducing ductility. This makes it difficult to grip the test specimens, which are more prone to fracture or slippage. Therefore, the test methodology must be adapted compared to non-irradiated materials.
Test specimen preparation was critical due to fiber orientation and tab quality, in accordance with ASTM D3039. Each material required a different strategy:
Initial tests were carried out in CERN cryostats, immersing the test piece and clamps in liquid nitrogen (77 K). Although the self-adjusting clamps worked in most cases, the brittleness of the irradiated test pieces pushed their capacity to the limit: too much pressure caused breakage, too little pressure caused slippage.
Material C presented the biggest problem due to the embrittlement of the matrix after irradiation. Slippage was exacerbated by thermal contraction in liquid nitrogen and the high investment in each specimen (only one per condition). This made it necessary to develop an alternative gripping system that would prevent slippage even in very brittle specimens.
To solve the slippage issue in irradiated specimens, Applus+ Laboratories developed a system that keeps the central area of the specimen submerged in liquid nitrogen (77 K) while the ends remain at room temperature, secured with conventional hydraulic clamps. The design includes a flexible cryogenic-compatible chamber, continuous LN₂ supply, and sensors to monitor the temperature.
The system was adapted to universal testing machines, allowing high clamping pressure without nitrogen leaks. Its open design facilitates the installation of additional sensors and reduces LN₂ consumption by cooling only the area of interest.
Two configurations were used:
The test specimens were thermally conditioned to ensure uniformity at 77 K. The temperature was verified with distributed sensors before applying controlled load, adjusting the speed according to the material. During the test, load, displacement, and temperature were monitored in real time. After the test, a detailed failure mode analysis was performed to validate the results.
The test campaign validated two methodologies:
The combination of both methods made it possible to obtain reliable data under post-irradiation cryogenic conditions, overcoming technical challenges and optimizing the use of irradiated material.
The localized cryogenic containment system developed by Applus+ Laboratories represents a key innovation: cooling only the test area while using conventional hydraulic grips. This resolved the conflict between high clamping pressure and material brittleness.
The tests carried out showed that the clamping system is a determining factor in the validity of the results, especially in materials that have been irradiated and subjected to cryogenic temperatures. Irradiation modifies stiffness and ductility, which increases fragility in the gripping areas and reduces tolerance to high pressures. Added to this is thermal contraction in liquid nitrogen, which alters the coefficient of friction and the interaction between the test piece, heels, and jaws.
In this context, the grip design must balance two opposing requirements:
The project experience demonstrated that standard protocols are not sufficient for these extreme conditions. The solution developed by Applus+ Laboratories, which combines localized cooling with conventional hydraulic jaws, redefines the traditional approach, offering greater control and reliability. This learning underscores the need to consider the clamping system as an integral part of the experimental design, rather than a secondary element.
The methodologies developed can be applied to other nuclear fusion projects, reducing dependence on large facilities and accelerating the qualification of materials under extreme conditions.
This project has enabled significant progress in the characterization of irradiated composite materials for nuclear fusion applications, facing extreme conditions that combine cryogenics, irradiation, and high mechanical demands. Among the main achievements are:
This work demonstrates the importance of technological collaboration. The synergy between ITER, CERN, and Applus+ Laboratories, together with the support of Fusion for Energy and Carlos III University of Madrid, has been key to overcoming seemingly insurmountable challenges. The solutions developed not only contribute to the advancement of the ITER project, but also open up new possibilities for democratizing access to specialized cryogenic testing, accelerating the qualification of materials for fusion energy.
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