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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
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Corporate powerhouses join pledge to triple nuclear energy by 2050
Following in the steps of an international push to expand nuclear power capacity, a group of powerhouse corporations signed and announced a pledge today to support the goal of at least tripling global nuclear capacity by 2050.
D. Rozzia, G. Bonny, S. Billiet, B. Boer, M. Verwerft
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 324-353
Research Article | doi.org/10.1080/00295450.2023.2229186
Articles are hosted by Taylor and Francis Online.
This paper presents the fuel performance simulation of two past experiments that are concerned with partial fuel melting. The activity is conducted in the framework of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Power to Melt and Maneuverability (P2M) – Second Framework for Irradiation Experiments (FIDES-II) Joint ExpErimental Programme (JEEP). The xM3 transient experiment involved uranium oxide (UO2) fuel with a ZIRconium Low Oxidation alloy (ZIRLO) cladding base irradiated up to 27 MWd/kg U, followed a ramp test up to 70 kW/m leading to inception of melting. The High Burnup Chemistry Experiment 4 (HBC4) transient was performed according to a rapid power ramp, on a UO2 fuel with a Zircaloy-4 cladding base irradiated up to 47 MWd/kg U. The linear heat generation rate reached 66.3 kW/m at the end of the transient leading to inception of melting and rodlet failure. Three main cases per each of the two transients were modeled with the TRANSURANUS code version 2015 in agreement with the benchmark specifications to consider uncertainty on the power during the ramping phases. The paper presents and discusses the analysis of these tests and provides an in-depth sensitivity analysis to assess the capabilities of the code as well as the effect of user choices in simulating the base irradiation and the inception of melting in light water reactor fuel rods.
