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2025: The year in nuclear
As Nuclear News has done since 2022, we have compiled a review of the nuclear news that filled headlines and sparked conversations in the year just completed. Departing from the chronological format of years past, we open with the most impactful news of 2025: a survey of actions and orders of the Trump administration that are reshaping nuclear research, development, deployment, and commercialization. We then highlight some of the top news in nuclear restarts, new reactor testing programs, the fuel supply chain and broader fuel cycle, and more.
A. Chaieb, R. Largenton, A. Ambard, B. Baurens, M. Ton That
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 232-244
Research Article | doi.org/10.1080/00295450.2023.2232664
Articles are hosted by Taylor and Francis Online.
CYRANO3 is the thermal-mechanical industrial code developed and used by Electricité de France (EDF) to simulate nuclear fuel rod performance under normal and transient conditions (power ramp tests) in pressurized water reactors and during transport and storage periods, as well. This code has already been successfully used by EDF for the last 30 years to justify normal operations and category 2 transients, covering various types of fuels: UO2, UO2 + gadolinium, mixed oxide, and various claddings, as well those proposed by nuclear fuel suppliers: Zircaloy-4, Zirlo,™ and Optimized Zirlo.™
The CYRANO3 code was recently improved to allow for modeling fuel melting. In this paper, a global overview of CYRANO3’s ability to simulate past power-to-melt (P2M) ramps is presented with a focus on recent developments carried out to assess fuel rod behavior under these conditions. CYRANO3 is demonstrated to be a powerful tool to provide reliable values of melted radii.
As part of validation of these development works, CYRANO3 calculations have been used to assess two P2M ramp experiments carried out in the BR2 experimental core in Belgium (HBC-4 P2M ramp), and in the R2 experimental core in Sweden (xM3 P2M ramp). The main objectives of the work are to expand knowledge of the thermal-mechanical behavior of high-burnup fuel under P2M ramps by making interpretations of test simulations and to validate newly developed computational models for fuel melting that have been implemented in an extended version of the CYRANO3 fuel code.
For both rods, the steady-state irradiation power history was captured and modeling was performed. The key results of the steady-state irradiation modeling are reproduced with fair accuracy by means of CYRANO3 simulations. The results demonstrate the good ability of CYRANO3 to simulate P2M ramps. The melted radii and conditions of failure are well predicted. Calculated melted radius at ramp terminal Linear Heat Generation Rate (LHGR) is in good agreement with the experimental measurements performed after the experiments.