Link between material properties and integrity assessment of NPP components within EU funded projects APAL, INCEFA-SCALE and FRACTESUS

Deep understanding of aging of the most important nuclear power plant (NPP) components and their material degradation on the one hand and development of advanced methods of the assessment of those components’ integrity and lifetime on the other hand is the only way to ensure safe operation of NPPs for long-term operation (LTO). The most significant degradation mechanisms are fatigue and irradiation embrittlement. Within Euratom research and training programme HORIZON 2020, several projects were running in several past years focussed on the research of the above-mentioned degradation mechanisms and on the way of assessing their impact. Three such projects are described in this paper: APAL ( A dvanced P TS A nalysis for L TO) project addresses challenges associated with multidisciplinary character of the pressurised thermal shock (PTS) analyses (both deterministic and probabilistic) and quantification of safety margins, INCEFA-SCALE ( IN creasing safety in NPPs by C overing gaps in E nvironmental F atigue A ssessment – focusing on gaps between laboratory data and component SCALE ) aims to improve assessments of fatigue lifetime of nuclear power plant components when subjected to environmentally assisted fatigue (EAF) loading and to provide guidance on the transferability of laboratory scale testing results to component-scale, FRACTESUS ( Frac ture mechanics te sting of irradiated RPV steels by means of su b-sized s pecimens) aims to determine the effect of specimen size on the fracture toughness properties. Large inter-laboratory testing is included to prove the repeatability and reproducibility of the small-scale testing of fracture toughness properties. Finite element models (FEM) are used to support the experimental results.

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Publication Details

Journal
EPJ Nuclear Sciences & Technologies
Published
2025-01-01
DOI
https://doi.org/10.1051/epjn/2025015
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
0.00

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article

Link between material properties and integrity assessment of NPP components within EU funded projects APAL, INCEFA-SCALE and FRACTESUS

Vladislav Pištora, G. Bonny, Alec McLennan
EPJ Nuclear Sciences & Technologies
Graphite, nuclear technology, radiation studies
article

Link between material properties and integrity assessment of NPP components within EU funded projects APAL, INCEFA-SCALE and FRACTESUS

Vladislav Pištora, G. Bonny, Alec McLennan
article en

Abstract

Deep understanding of aging of the most important nuclear power plant (NPP) components and their material degradation on the one hand and development of advanced methods of the assessment of those components’ integrity and lifetime on the other hand is the only way to ensure safe operation of NPPs for long-term operation (LTO). The most significant degradation mechanisms are fatigue and irradiation embrittlement. Within Euratom research and training programme HORIZON 2020, several projects were running in several past years focussed on the research of the above-mentioned degradation mechanisms and on the way of assessing their impact. Three such projects are described in this paper: APAL ( A dvanced P TS A nalysis for L TO) project addresses challenges associated with multidisciplinary character of the pressurised thermal shock (PTS) analyses (both deterministic and probabilistic) and quantification of safety margins, INCEFA-SCALE ( IN creasing safety in NPPs by C overing gaps in E nvironmental F atigue A ssessment – focusing on gaps between laboratory data and component SCALE ) aims to improve assessments of fatigue lifetime of nuclear power plant components when subjected to environmentally assisted fatigue (EAF) loading and to provide guidance on the transferability of laboratory scale testing results to component-scale, FRACTESUS ( Frac ture mechanics te sting of irradiated RPV steels by means of su b-sized s pecimens) aims to determine the effect of specimen size on the fracture toughness properties. Large inter-laboratory testing is included to prove the repeatability and reproducibility of the small-scale testing of fracture toughness properties. Finite element models (FEM) are used to support the experimental results.

EPJ Nuclear Sciences & TechnologiesVol. 11
Belgian Nuclear Research Centre (BE), Nuclear Research Institute Rez (Czechia) (CZ)
European Commission, Euratom Research and Training Programme, Japan Atomic Energy Agency, H2020 Euratom
Openalex Percentile: Top 93%
Graphite, nuclear technology, radiation studies
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