Формування удосконаленого підходу до оцінки крихкої міцності корпусу реактора
Within the framework of the Research and Training Program (2024), Euroatom’s international project Advanced PTS Analysis for LTO (APAL project) was launched in October 2020 and completed in spring 2024. The State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS) actively pa...
Збережено в:
| Дата: | 2025 |
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| Автори: | , , , , , |
| Формат: | Стаття |
| Мова: | Ukrainian |
| Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2025
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| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/1270 |
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| Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation Safety| Резюме: | Within the framework of the Research and Training Program (2024), Euroatom’s international project Advanced PTS Analysis for LTO (APAL project) was launched in October 2020 and completed in spring 2024. The State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS) actively participated in this project, focusing on the assessment of thermalhydraulic, as well as strength safety aspects of the reactor vessel under emergency scenarios involving core cooling.
The main goals of the project are to:
develop an advanced approach to assessing brittle fracture resistance of the reactor pressure vessel both at the stage of design operation and during long-term operation, evaluate the main factors that influence the analysis results for thermal shock with further improvement of methods for analyzing brittle fracture resistance;
apply up-to-date deterministic and probabilistic analysis methods (including analysis of uncertainties in thermalhydraulic calculations and quantitative assessment of brittle fracture safety margin).
The APAL project team managed to improve the approaches to strength justification at the stage of long-term operation for pressurized water reactors and develop a guideline with best practices based on the experience of the countries involved in the implementation of the APAL project. On the basis of the analysis performed, existing approaches to analyzing thermal shock of the pressurized reactor vessel were summarized and possible improvements (measures) for the implementation at NPPs that reduce the effect of thermal shock and contribute to further safe long-term operation were identified. The experience and lessons learned obtained in the framework of the APAL project can be used by experts of the Operating Organization, Nuclear Regulatory Authorities and Technical Support Organizations. |
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