Використання теплогідравлічного коду TRACE для моделювання малих модульних реакторів
Over the past decades, the development of nuclear energy has been marked by growing interest in Small Modular Reactors (SMRs), which are viewed as a promising solution to address several limitations inherent to conventional large-scale nuclear power plants. SMRs offer a range of advantages, includin...
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| Datum: | 2025 |
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| Hauptverfasser: | , |
| Format: | Artikel |
| Sprache: | Ukrainian |
| Veröffentlicht: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2025
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| Online Zugang: | https://nuclear-journal.com/index.php/journal/article/view/1269 |
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| Назва журналу: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Zusammenfassung: | Over the past decades, the development of nuclear energy has been marked by growing interest in Small Modular Reactors (SMRs), which are viewed as a promising solution to address several limitations inherent to conventional large-scale nuclear power plants. SMRs offer a range of advantages, including reduced capital costs, shorter construction time, and enhanced safety due to the adoption of advanced concepts in Generation IV reactors and the broader implementation of passive safety systems in light water reactor designs. As of 2024, the IAEA’s Advanced Reactors Information System (ARIS) and dedicated SMR catalogues contain data on approximately 70 projects, including land-based, marine-based reactors and microreactors. Some of these projects, such as the NuScale SMR (USA), BWRX-300 (General Electric Hitachi) and the Rolls-Royce SMR, have already received design approval or completed pre-licensing safety assessments.
However, the development of SMRs presents serious challenges related to the lack of operational experience and the need for comprehensive safety justification. This requires extensive research and development efforts combining analytical and experimental studies to confirm the applicability of existing computational tools for modeling the behavior of these novel reactors under both normal and accident conditions and to justify acceptability of features implemented in the design.
A notable example addressing these issues is the MASLWR (Multi-Application Small Light Water Reactor) experimental project launched in 2000 with the support of the U.S. Department of Energy. As part of the project, the OSU-MASLWR experimental facility was established to study natural circulation and system behavior under accident scenarios. The results obtained from this facility formed the basis of the NuScale SMR design, which was approved by the U.S. Nuclear Regulatory Commission in 2020. Despite the completion of project, OSU-MASLWR continues to serve as an international research platform. In 2010, the IAEA initiated the so-called International Collaborative Standard Problem (ICSP) at this facility to assess the capabilities of modern thermohydraulic codes in modeling integral reactor designs. Although Ukraine did not participate in the ICSP at the time, given the public statements of SE NNEGC “Energoatom” regarding potential SMR deployment in Ukraine, the management of the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS) has initiated modeling and post-test calculations of OSU-MASLWR experiments as part of the SSTC NRS research program.
The objective of this work is to gain experience in modeling heat removal processes in an integral SMR during accidents using the TRACE system thermohydraulic code and to evaluate the code fundamental capability to simulate systems based on natural circulation. This paper presents selected results of the SSTC NRS analysis of one OSU-MASLWR experiment related to total loss of feedwater to the steam generator performed using the TRACE code. |
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