Structural Materials
The safety of nuclear reactors critically depends on the mechanical behavior of structural materials under harsh environmental conditions (neutron irradiation, high temperatures). In the framework of the program NUSAFE (Nuclear Waste Management, Safety and Radiation Research) of the Helmholtz Association we characterize irradiated reactor materials from the nm-scale to the macro-scale. Our focus:
- Long-term irradiation effects in reactor pressure vessel steels of running and new-build reactors in the context of lifetime extension
- Assessment of the irradiation tolerance of innovative materials for future reactor concepts including nuclear fusion (e.g. ferritic/martensitic Cr-steels, oxide dispersion strengthened (ODS) steels, the emerging class of high-entropy alloys)
The methodical spectrum covers the full functional chain from nm-scale irradiation-induced defects to macroscopic mechanical properties and aims at the identification, better understanding and mitigation of irradiation effects. The new insight substantially contributes to the scientific background for the safety assessment of nuclear reactors. The research relies on a unique infrastructure including the hot cell labs for the investigation of neutron-irradiated materials as well as the HZDR Ion Beam Center for ion irradiation experiments.
Our expertise:
- Mechanical testing of irradiated materials
- Nano-/Microstructure characterization of irradiated materials
- Ion irradiation to emulate neutron irradiation effects
Current projects
- Innovative structural materials for fission and fusion
(INNUMAT, EU, HORIZON-EURATOM, 2022-2026) - European Database for Multiscale Modelling of Radiation Damage
(ENTENTE, EU-H2020-Euratom, 2020-2024) - Fracture mechanics testing of irradiated RPV steels by means of sub-sized specimens
(FRACTESUS, EU-H2020-Euratom, 2020-2024) - Structural Materials research for safe Long Term Operation of LWR NPPs
(STRUMAT-LTO, EU-H2020-Euratom, 2020-2024) - Untersuchungen zum Ausheilverhalten von Reaktordruckbehälterstählen bei niedrigen Temperaturen
(WetAnnealing, BMWI, 2020-2025) - Physical modelling and modelling-oriented experiments for structural materials 2
(IOANIS2, EERA-JPNM Pilote Project, 2023 - 2027, coordinator HZDR) - In-situ experiments for nuclear applications
(INSITEX, EERA-JPNM Pilote Project, 2023 - 2027) - On the use of small punch as high-throughput screening technique to extract mechanical properties of ion irradiated materials
(SHERPA, EERA-JPNM Pilote Project, 2023 - 2027)
Latest Publication
Master Curve reference temperature behavior of steels with varying Ni/Mn content and subjected to a fluence of 11x10E19 neutron/cm²
Lindqvist, S.; Kolluri, M.; Cinger, D.; Zarazovskii, M.; Szabolcs, S.; Altstadt, E.
Abstract
The degradation of fracture toughness due to irradiation needs to be understood to assess the structural integrity of reactor pressure vessels for long-term operation. The level of degradation is dependent on the chemical content, particularly of elements like Ni and Mn. The fracture toughness properties for three types of steels (i.e. VVER-1000 steel, western model steel and VVER-1000 welds) with varying contents of Ni and Mn were characterized based on Master Curve T0 reference temperature in reference condition and in irradiated condition. The results show that, in the high fluence region, the shifts in T0 correlate with the content of Ni and Mn, and the scatter in fracture toughness is mostly consistent for the reference and irradiated conditions. At higher T0 values, above 75 °C, T41J gives an increasingly larger estimate compared to T0. The obtained results can be applied to develop new improved embrittlement trends curves for NPP lifetime assessment.
Keywords: High fluence; Ni and Mn; Fracture toughness; Master Curve; Homogeneity
-
International Journal of Pressure Vessels and Piping 214(2025), 105421
Online First (2024) DOI: 10.1016/j.ijpvp.2024.105421
Downloads
- Secondary publication expected from 02.01.2026
Permalink: https://www.hzdr.de/publications/Publ-40371
Team
Head | |||||
Name | Bld./Office | +49 351 260 | |||
---|---|---|---|---|---|
Dr. Eberhard Altstadt | 801/P151 | 2276 | e.altstadt![]() | ||
Dr. Cornelia Kaden | 801/P102 | 3431 | c.kaden@hzdr.de, c.heintze![]() | ||
Employees | |||||
Name | Bld./Office | +49 351 260 | |||
Dr. Frank Bergner | 801/P150 | 3186 | f.bergner![]() | ||
Dr. Paul Chekhonin | 801/P146 | 2149 | p.chekhonin![]() | ||
Vanessa Dykas | 801/P105 | 3363 | v.dykas![]() | ||
Mario Houska | 801/P148 | 2242 | m.houska![]() | ||
Jens Pietzsch | 801/P032 | 2814 3550 | jens.pietzsch![]() | ||
Dr. Andreas Ulbricht | 801/P146 | 3155 | a.ulbricht![]() | ||
Tilo Welz | 801/P032 | 2814 | t.welz![]() |
Latest publication
Master Curve reference temperature behavior of steels with varying Ni/Mn content and subjected to a fluence of 11x10E19 neutron/cm²
Lindqvist, S.; Kolluri, M.; Cinger, D.; Zarazovskii, M.; Szabolcs, S.; Altstadt, E.
Abstract
The degradation of fracture toughness due to irradiation needs to be understood to assess the structural integrity of reactor pressure vessels for long-term operation. The level of degradation is dependent on the chemical content, particularly of elements like Ni and Mn. The fracture toughness properties for three types of steels (i.e. VVER-1000 steel, western model steel and VVER-1000 welds) with varying contents of Ni and Mn were characterized based on Master Curve T0 reference temperature in reference condition and in irradiated condition. The results show that, in the high fluence region, the shifts in T0 correlate with the content of Ni and Mn, and the scatter in fracture toughness is mostly consistent for the reference and irradiated conditions. At higher T0 values, above 75 °C, T41J gives an increasingly larger estimate compared to T0. The obtained results can be applied to develop new improved embrittlement trends curves for NPP lifetime assessment.
Keywords: High fluence; Ni and Mn; Fracture toughness; Master Curve; Homogeneity
-
International Journal of Pressure Vessels and Piping 214(2025), 105421
Online First (2024) DOI: 10.1016/j.ijpvp.2024.105421
Downloads
- Secondary publication expected from 02.01.2026
Permalink: https://www.hzdr.de/publications/Publ-40371
Team
Head | |||||
Name | Bld./Office | +49 351 260 | |||
---|---|---|---|---|---|
Dr. Eberhard Altstadt | 801/P151 | 2276 | e.altstadt![]() | ||
Dr. Cornelia Kaden | 801/P102 | 3431 | c.kaden@hzdr.de, c.heintze![]() | ||
Employees | |||||
Name | Bld./Office | +49 351 260 | |||
Dr. Frank Bergner | 801/P150 | 3186 | f.bergner![]() | ||
Dr. Paul Chekhonin | 801/P146 | 2149 | p.chekhonin![]() | ||
Vanessa Dykas | 801/P105 | 3363 | v.dykas![]() | ||
Mario Houska | 801/P148 | 2242 | m.houska![]() | ||
Jens Pietzsch | 801/P032 | 2814 3550 | jens.pietzsch![]() | ||
Dr. Andreas Ulbricht | 801/P146 | 3155 | a.ulbricht![]() | ||
Tilo Welz | 801/P032 | 2814 | t.welz![]() |