VVER long-term operation – A review based on the material studies results from past and ongoing EU-supported research projects

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-03-01 DOI:10.1016/j.nucengdes.2025.113949

Vladimir Slugen , Jana Simeg Veternikova , Maria Domankova , Matus Gavalec , Jana Petzova , David Slnek , Mykola Dzubinsky , Oleksii Shugaylo , Ildiko Szenthe , Ferenc Gillemot , Maksym Zarazovskii , Jari Lydman , Radim Kopriva , Szabolcs Szavai , Ondrej Srba

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Abstract

Safe and long-term operation (LTO) of nuclear power plants (NPP) with Water-Water Energetic Reactors (VVER) is essential for several central and eastern European countries to keep their energy supply security. During the last decades, several EU-supported projects in framework projects or Horizon2020 schemes have focused on the material degradation of pressurised water reactors (PWRs), especially VVERs. This paper aims to extract the most important results dominantly from EURATOM projects which support or could limit the long-term operation of this Soviet design of PWRs. The accent is given on ongoing projects such as FRACTESUS, STRUMAT-LTO, APAL, and ENTENTE. Actually, running project DELISA-LTO (2022–2026) comprises not only results from previous research in this area but also incorporates wide material databases coming from nuclear power plant V-1 in Jaslovské Bohunice (Slovakia), which was shut down after 28 years of operation and provides wide-range of original service-aged materials specimens for profound material studies having in mind lifetime extension of VVERs. Consolidated knowledge focused mainly on the reactor pressure vessel (RPV) material studies is summarised and supported by relevant references.

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VVER长期运行-基于过去和正在进行的欧盟支持的研究项目的材料研究结果的审查

水-水能堆（VVER）核电站的安全、长期运行（LTO）对一些中东欧国家保障能源供应安全至关重要。在过去的几十年里，几个欧盟支持的框架项目或Horizon2020计划的项目都专注于压水反应堆（pwr）的材料降解，特别是vver。本文旨在主要从欧洲原子能共同体项目中提取支持或可能限制这种苏联设计的压水堆长期运行的最重要结果。重点是正在进行的项目，如FRACTESUS、STRUMAT-LTO、APAL和ENTENTE。实际上，运行DELISA-LTO项目（2022-2026）不仅包括该领域以前的研究成果，还包括来自jaslovsk Bohunice（斯洛伐克）的V-1核电站的广泛材料数据库，该核电站在运行28年后关闭，并为深入的材料研究提供了广泛的原始服务老化材料样本，考虑到vver的寿命延长。综合知识主要集中在反应堆压力容器（RPV）材料的研究总结和相关参考文献的支持。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.