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The busyness of the nuclear fuel supply chain
Ken Petersenpresident@ans.org
With all that is happening in the industry these days, the nuclear fuel supply chain is still a hot topic. The Russian assault in Ukraine continues to upend the “where” and “how” of attaining nuclear fuel—and it has also motivated U.S. legislators to act.
Two years into the Russian war with Ukraine, things are different. The Inflation Reduction Act was passed in 2022, authorizing $700 million in funding to support production of high-assay low-enriched uranium in the United States. Meanwhile, the Department of Energy this January issued a $500 million request for proposals to stimulate new HALEU production. The Emergency National Security Supplemental Appropriations Act of 2024 includes $2.7 billion in funding for new uranium enrichment production. This funding was diverted from the Civil Nuclear Credits program and will only be released if there is a ban on importing Russian uranium into the United States—which could happen by the time this column is published, as legislation that bans Russian uranium has passed the House as of this writing and is headed for the Senate. Also being considered is legislation that would sanction Russian uranium. Alternatively, the Biden-Harris administration may choose to ban Russian uranium without legislation in order to obtain access to the $2.7 billion in funding.
Marco Riva, Alice Ying, Mohamed Abdou, Mu-Young Ahn, Seungyon Cho
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1037-1045
Technical Paper | doi.org/10.1080/15361055.2019.1643691
Articles are hosted by Taylor and Francis Online.
In this paper, dynamic tritium flow rates and inventories of the outer fuel cycle (OFC) of a DEMOnstration nuclear fusion reactor (DEMO) are analyzed to determine the initial amount of tritium that has to be prepared to sustain plasma operation at reactor start-up, i.e., until tritium bred in blankets is extracted and available. The main components of the helium coolant ceramic reflector tritium breeding system were modeled in detail with the use of COMSOL Multiphysics and integrated into a system-level model within the MATLAB/Simulink platform to simulate OFC tritium streams. Furthermore, a control volume analysis was derived to incorporate the OFC flow rates calculated with the dynamic integrated numerical tool for initial start-up tritium inventory (ISTI) analysis. We found that the tritium processing time of the tritium extraction system (TES) plays a critical role for ISTI assessment. On one hand, for batchwise technology such as adsorption/regeneration columns, the OFC-attributed ISTI is ~2.6 kg calculated for a 3-GW fusion power reactor. On the other hand, online extraction techniques such as catalytic membrane reactors offer continuous operation and result in ~10 to 250 g of ISTI depending on the TES efficiency and breeder material tritium residence time. The helium coolant system (HCS) line has a minor impact on ISTI since tritium retention in HCS components is orders of magnitude lower than the TES line when a tungsten plasma-facing-component coating is implemented.