Benchmarking of Structural Materials Pre-selected for Advanced Nuclear Reactors.
Closed for Proposals
Project Type
Coordinated Research ProjectProject Code
F11014
CRP
1750
Approved Date
22/02/2011Project Status
ClosedStart Date
19/04/2011Expected End Date
31/05/2014Completed Date
09/10/2015Description
To enhance the future role of nuclear energy systems, several innovative reactor designs have been proposed (e.g. Generation IV, INPRO, ADS or ITER). These new systems would enhance sustainability and reduce radioactive wastes in the nuclear fuel cycle, further enhance reactor safety, improve economics for electricity production and new applications such as the supply of process heat and/or hydrogen production, and increase proliferation resistance. The operating regimes for the structural materials in these innovative new reactor concepts extend to higher temperatures and irradiation doses than in existing power reactors and the design life will be extended to at least 60 years. In addition, some new coolants provide potentially more aggressive environment. In order to achieve these objectives, durable and expensive works, as well as intensive information exchange, are needed to develop and qualify new materials for key structural components. Therefore, international efforts should be concentrated on testing new materials. Several recently developed structural materials have very promising characteristics, especially for application in primary components of innovative nuclear reactors. Among these are reduced activation ferritic-martensitic steels and vanadium alloys, oxide dispersion strengthened (ODS) steels, and silicon-carbide composites (SiC). Special attention should be given to materials for the nuclear fuel cladding and the reactor vessel since they act as the main barriers to release of fission products. For these and other innovative materials, continued activities related to research, development and qualification are urgently needed, hence coordinated research efforts of candidate materials should be initiated. These efforts should combine studies of their long-term stability and microstructural behaviour. Today there is clear evidence of high interest from many Member States, and various research groups would like to directly contribute to planned Round-Robin exercise in order to fully characterise and test recently developed ODS class of steels for fission and fusion applications.
Objectives
Application of nuclear techniques for characterisation and analysis of materials for nuclear technologies, supporting emerging advanced design as well as nuclear fuel cycle technologies for advanced and innovative reactors. The objective of the project 1.4.3.2 (NAPC), 1.2.4.1 (NEFW) and 1.1.5.3 (NENP) under which the CRP is being proposed is:To increase the capacity of Member States to utilize frontline nuclear techniques and key nuclear facilities to support their research and development needs;To harmonize and qualify experimental techniques and methods;To establish international consensus in the developmental efforts on advanced nuclear fuel cycle technologies.
Specific Objectives
To investigate and fully characterize the material properties in the framework of coordinated research (test matrix);
To bring together scientists and engineers in order to share knowledge and enhance the capacity building in the application of nuclear techniques for investigation and characterisation of materials and components relevant to innovative reactor systems.
To formulate recommendations for harmonized characterization of materials (including testing methodology) and proposal for further improvement of fabrication and processing;
To create a material database of qualified tests (mechanical tests and microstructure characterisation);
To fabricate and distribute the agreed samples of supplied ODS materials for Round-Robin testing;
Impact
A large network of institutions was assembled with a complex set of mutually dependent tests. While many results have been published, the aim of producing a comprehensive database of properties of ODS steels within a three-to-four-year CRP were probably too ambitious. The lack of documentation internally and externally means the CRP "died" when the POs who ran it when it was "live" left.
Relevance
The CRP was extremely relevant to the development of oxide-dispersed strengthened mechanical alloys which have promising applications in fast reactors and fusion systems.
CRP Publications
Czech Republic
Paper
2013
SLUGEN, V. - VETERNIKOVA, J. – DEGMOVA, J. – KILPELAINEN, S. - TUOMISTO, F. – KRSJAK, V.: Vacancy type defects in oxide dispersion strenghtened steels. In: Material Science Forum 733 (2013), 264-269
China, Japan
Conference
2011
C.H. Zhang, A. Kimura, R. Kasada, J. Jang, H. Kishimoto, Y.T. Yang, "Characterization of the Oxide particles in Al-added high-Cr ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 221-224, 14th International Conference on Fusion Reactor Materials (ICFRM-14),
Japan
Paper
2011
Peng Dou, Akihiko Kimura, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe, "Effects of extrusion temperature on the nano-mesoscopic structure and mechanical properties of an Al-alloyed high-Cr ODS ferritic steel", Journal of Nuclear Materials, 417 (2011) 166-170
Russia
Paper
2013
R. A. Ryazhanov, J. O'Connell, V. A. Skuratov, A. S. Sohatsky, J. H. Neethling, A. E. Volkov, K. Havancsak. Effect of swift heavy ion irradiation on transformations of oxide nanoclusters in ODS alloys. Phys. Status Solidi C 10 (2013), No. 4, 681–684
Czech Republic
Paper
2011
KRSJAK,V. – SOJAK, S. – SLUGEN, V. – PETRISKA, M.: Ion implantation induced defects in Fe-Cr alloys studied by conventional positron annihilation lifetime spectroscopy. In: Journal of Physics: Conference eries 265 (2011) 012029
Japan, Germany, Korea
Paper
2011
L.Hsiung, M. Fluss, S. Tumey, J. Kuntz, B. El-Dasher, M. Wall, B. Choi, A. Kimura, F. Willaime, Y. Serruys, "HRTEM study of Oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance", Journal of Nuclear Materials, 409 (2011) 72-79.
Romania
Conference
2013
Maria Mihalache, Manuela Fulger, Alice Dinu, Constantin Paunoiu, Zhangjian Zhou, Mihail Mihalache Investigation of the Oxides Formed on 304L ODS Steel and 304L SS in Supercritical Water Environment ICIT international conference on progress in cryogenics and isotopes separation Calimanesti-Caciulata (Romania) ICSI 2012, 29-31 Oct , ISSN: 1582-2575,
Japan
Paper
2011
L.H. Lee, R. Kasada, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe, "Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 1225-1228,
Japan, Korea
Paper
2011
Sanghoon Noh, Ryuta Kasada, Akihiko Kimura, Seung Hwan C. Park, Satoshi Hirano, "Microstructure and mechanical properties of friction stir processed ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 245-248
Czech Republic
Paper
2012
SABELOVA, V. – PETRISKA, M. - VETERNIKOVA, J. - SLUGEN, V. – DEGMOVA, J. - KILPELAINEN, S.: Defect detection in Fe-Cr alloys with positron annihilation Doppler broadening spectroscopy. In: Material Science Forum 733 (2013), 270-273
China
Paper
2014
R. Coppola, J. Rodriguez-Carvajal, M. Wang, G. Zhang, Z. Zhou, High resolution neutron diffraction crystallographic investigation of Oxide Dispersion Strengthened steels of interest for fusion technology, Journal of Nuclear Materials 455 (2014) 426–430
China
Paper
2013
H.L. Hu, Z.J. Zhou, L. Liao, L.F. Zhang, M. Wang, S.F. Li, Corrosion behavior of a 14Cr-ODS steel in supercritical water, Journal of Nuclear Materials 437 (2013) 196–200
Romania
Conference
2013
Maria Mihalache, Manuela Fulger, Marian Pantaru, Mihail Mihalache, Zhangjian Zhou Effect of Different Austenite Stabilizers on Oxide Morphology Grown in Supercritical Water on ODS Steels - SIEN 2013 International Symposium on Nuclear Energy, Bucharest, Romania, 10-14 November 2013
Russia
Paper
2013
Ryazanov AI, Chugunov OK, Ivanov SM, Latushkin ST, Lindau R, M?slang A, Nikitina AA, Prikhodko KE, Semenov EV, Unezhev VN, Vladimirov PV. Tensile properties and microstructure of helium implanted EUROFER ODS. Journal of Nuclear Materials. 2013 Nov 1;442(1-3):S153-7.
Japan
Paper
2011
R. Kasada, S.G. Lee, J. Isselin, J.H. Lee, T. Omura, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe, "Anisotropy in tensile and ductile–brittle transition behavior of ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 180-184
Ukraine
Conference
2013
Valentin Tsiar Oral report on work in CRP. 21th International Conference on Nuclear Engineering ICONE21 (July 29 – August 2, 2013, Chengdu, China)
Ukraine
Paper
2014
Valentyn Tsisar, Olga Yeliseyeva, Jürgen Konys, "Oxidation / dissolution of ferritic ODS steels in static lead with various oxygen content at 650°C", Nuclear Engineering and Design 280 (2014) 673–679.
Czech Republic
Paper
2012
VETERNIKOVA, J. – CHUDY, M. – SLUGEN, V. - EISTENER, M. – WEBER, H. W. – SOJAK, S. – HINCA, R. – DEGMOVA, J. – SABELOVA, V.: Positron Annihilation Lifetime Spectroscopy Study of neutron Irradiated High Temperature Supeconductors YBa2Cu3O7-d for application in Fusion Facilities. In: Journal of Fusion Energy 31 (2012), 89-95
Czech Republic
Conference paper
2012
SOJAK, S. - SLUGEN, V. – KRSJAK, V. – EGGER, W. – RAVELLI, L. – PETRISKA, M. – STANCEK, S. – SKARBA, M. – PRIPUTEN, P. – VITAZEK, K. – STACHO, M. - VETERNIKOVA, J. – SABELOVA, V.: PLEPS study of thermal annealing influence on binary Fe-11,62% Cr alloys. In: Proceedings from 18th International Conference of Applied Physics of Condesed Matter APCOM2012, ?trbské Pleso, 20.-22.6.2012, p.91-94
Japan, Korea
Paper
2012
Sanghoon Noh, Byungjun Kim, R. Kasada, A. Kimura, “Diffusion bonding between ODS ferritic steel and F82H steel for fusion applications”, Journal of Nuclear Materials, 426 (1-3), (2012) 208-213.
China
Conference
2013
Man Wang, Zhangjian Zhou, Microstructure and tensile property assessment of ODS austenitic steels for SCWR core application , The 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6), March, 2013, Shenzhen, China
Japan
Paper
2011
A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C.H. Zhang, J. Isselin, P. Dou, J.H. Lee, N. Muthukumar, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T.F. Abe, "Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems", Journal of Nuclear Materials, 417 (2011) 176-179,
Japan
Paper
2011
J. Isselin, R. Kasada, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe, "Evaluation of fracture behavior of recrystallized and aged high-Cr ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 185-188
Czech Republic
Paper
2013
VETERNIKOVA, J. – KILPELAINEN, S. – SKARBA, M. - TUOMISTO,F. – SLUGEN, V. – DEGMOVA, J. – SABELOVA, V. - SOJAK, S.: Positron annihilation measurement performed on oxide-dispersion strenghtened steels. In: Material Science Forum 733 (2013), 278-281
Czech Republic
Paper
2012
VETERNIKOVA, J. – DEGMOVA, J. – KILPELAINEN, S. – SLUGEN, V. – TUOMISTO,F. – RAISANEN, J.- KRSJAK, V. – PETRISKA, M. – SOJAK, S. – HINCA, R. – STACHO, M.: Non-destructive examination of helium implanted HTRs contruction materials. Nuclear engineering and design 251 (2012), 354-359
Czech Republic
Conference paper
2011
PETRISKA, M. - SLUGEN, V. – KRSJAK,V. – ZEMAN, A.: Application possibilities of Acquiris digital card DP240 for positron lifetime measurement. In: Journal of Physics: Conference Series 265 (2011) 012014
Romania
Conference
2014
Maria Mihalache, Iulia Dumitrescu , Zhangjian Zhou - Mechanical properties of two austenitic and ferritic/martensitic steels strenghthened with dispersed oxides - PROCEEDINGS of NUCLEAR 2014 - Annual International Conference on Sustainable Development through Nuclear Research and Education, Pitesti, Romania, 28-31 May 2013, ISSN 2066-2955.
China
Paper
2012
Man Wang, Zhangjian Zhou, Helong Hu, Hongyin Sun, Effects of plastic deformations on microstructure and mechanical properties of ODS-310 austenitic steel, Journal of Nuclear Materials 430 (2012), pp. 259-263
European Commission (NRG)
Paper
2011
Nilsson, K-F, Martin O., Chenel-Ramos, C., Mendes. The segmented expanding cone-mandrel test revisited as material characterization and component test for fuel claddings. Nucl. Eng. Design, 241, (2011), 445-448
Ukraine
Paper
2013
Olga Yeliseyeva, Valentyn Tsisar, Zhangjian Zhou, "Corrosion behavior of Fe–14Cr–2W and Fe–9Cr–2W ODS steels in stagnant liquid Pb with different oxygen concentration at 550 and 650°C", Journal of Nuclear Materials 442 (2013) 434–443;
Japan
Paper
2011
N.Y. Iwata, T. Liu, P. Dou, R. Kasada, A. Kimura, T. Okuda, M. Inoue, F. Abe, S. Ukai, S. Ohnuki, T. Fujisawa, "Effects of MA environment on the mechanical and microstructural properties of ODS ferritic steels", Journal of Nuclear Materials, 417 (2011) 162-165
Romania
Conference
2013
Maria Mihalache, Manuela Fulger, Marian Pantaru, Mihail Mihalache, Zhangjian Zhou Effect of Different Austenite Stabilizers on Oxide Morphology Grown in Supercritical Water on ODS Steels - SIEN 2013 International Symposium on Nuclear Energy, Bucharest, Romania, 10-14 November 2013
Japan, USA, Spain
Paper
2011
Bassem El-Dasher, Joseph Farmer, James Ferreira, Magdalena Serrano de Caro, Alexander Rubenchik, Akihiko Kimura, "Corrosion of Oxide dispersion strengthened iron-chromium steels and tantalum in fluoride salt coolant: An in situ compatibility study for fusion and fusion-fission hybrid reactor concepts", Journal of Nuclear Materials, 419 (2011) 15-23.
Japan
Paper
2011
Naoko Oono, Sanghoon Noh, Noriyuki Iwata, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura, "Microstructures of brazed and solid-state diffusion bonded joints of tungsten with Oxide dispersion strengthened steel", Journal of Nuclear Materials, 417 (2011) 253-256
China
Paperr
2014
Shaofu Li, Zhangjian Zhou, Jinsung Jang, Man Wang, Helong Hu, Hongying Sun, Lei Zou, Guangming Zhang, Liwei Zhang, The influence of Cr content on the mechanical properties of ODS ferritic steels, Journal of Nuclear Materials 455 (2014) 194–200
China
Conference
2013
Shaofu Li, Zhangjian Zhou, et al, The effect of Cr content on the mechanical properties of ferritic ODS steels, The 16th Inter. Conference on Fusion Reactor materials (ICFRM-16), Oct. 2013, Beijing, China
Czech Republic
Conference paper
2012
VETERNIKOVA, J. – SLUGEN, V. - DEGMOVA, J. – SABELOVA, V. – PETRISKA, M. – STANCEK, S.: Positron study of implanted ODS steels. In: Proceedings from 18th International Conference of Applied Physics of Condesed Matter APCOM2012, ?trbské Pleso, 20.-22.6.2012, p.79-82
China
Paper
2015
Mengqiang Gong, Zhangjian Zhou, Helong Hu, Guangming Zhang, Shaofu Li, Man Wang, Effects of aluminum on microstructure and mechanical behavior of 14Cr–ODS steels, Journal of Nuclear Materials 462 (2015) 502–507
Czech Republic
Paper
2013
SOJAK, S. – SLUGEN, V. – KRSJAK, V. – EGGER, W. – RAVELLI, L. – PETRISKA, M. – STANCEK, S. – SKARBA, M. – PRIPUTEN, P. – VITAZEK, K. – STACHO, M. - VETERNIKOVA, J. - SABELOVA, V.: Thermal annealing influence on ions implanted Fe-Cr model alloys. In: Material Science Forum 733 (2013), 274-277
Romania
Conference
2013
Maria Mihalache, Alice Dinu, Manuela Fulger, Zhangjian Zhou, Mihail Mihalache Assessment and Comparison of Oxides Grown on 304L ODS Steel and 304L SS in Water Environment in Supercritical Conditions - PROCEEDINGS of NUCLEAR 2013 - Annual International Conference on Sustainable Development through Nuclear Research and Education, Pitesti, Romania, 25-27 May 2013, ISSN 2066-2955
China
Paper
2013
Man Wang, Zhangjian Zhou, Hongying Sun, Helong Hu, Shaofu Li, Microstructural observation and tensile properties of ODS-304 austenitic steel, Materials Science & Engineering A, 559 (2013) 287–292
Romania
Conference
2014
Mihalache M, Mihalache M, Dumitrescu I, Zhou Z. Assessment Oxidation Kinetics and Products in SCWR Media of Austenitic ODS Steels With Different Austenite Stabilisers. In2014 22nd International Conference on Nuclear Engineering 2014 Jul 7 (pp. V001T02A014-V001T02A014). American Society of Mechanical Engineers.
Ukraine
Conference
2012
Tsisar V, “Development of new structural materials for advanced fission and fusion reactor systems”, 16 - 20 April 2012, Ispra (Italy)
China
Paper
2013
Li S, Zhou Z, Wang M, Hu H, Zou L, Zhang G, Zhang L. Microstructure and mechanical properties of 16 Cr-ODS ferritic steel for advanced nuclear energy system. InJournal of Physics: Conference Series 2013 (Vol. 419, No. 1, p. 012036). IOP Publishing.
Czech Republic
Conference
2012
SABELOVá, V. – PETRISKA, M. – VETERNIKOVA, J. - SLUGEN, V. – SOJAK, S.: Application of Doppler broadening spectroscopy for detection of vacancy defects. In: 18th International Conference of Applied Physics of Condensed Matter APCOM2012, ?trbské Pleso, 20.-22.6.2012, p.75-78
European Commission (NRG)
Conference
2011
Novotny, R., H?hner, P., Moilanen P., Piipo J., Ripplinger S., Heftrich T., SCW facilities at JRC Petten – Past, Present and Future, The 5th Int. Sym. SCWR (ISSCWR-5), Vancouver, British Columbia, Canada,
Russia
Paper
2013
V.A. Skuratov, V.V. Uglov, J. O’Connell, A.S. Sohatsky, J.H. Neethling, S.V. Rogozhkin. Radiation stability of the ODS alloys against swift heavy ion impact. J. Nucl. Mater. 442 (1-3) (2013) 449-457.
China
Paper
2014
Zhang G, Zhou Z, Wang M, Li S, Zou L, Zhang L. Tensile and Charpy impact properties of an ODS ferritic/martensitic steel 9Cr–1.8 W–0.5 Ti–0.35 Y2O3. Fusion Engineering and Design. 2014 Apr 1;89(4):280-3.
Czech Republic
Conference Paper
2011
SLUGEN, V. – HINCA, R. – STACHO, M.: Positron annihilation techniques applied on reactor steels. In: Journal of Physics: Conference Series 265 (2011) 012008
China
Paper
2012
Helong Hu, Zhangjian Zhou, et al, Study of the corrosion behavior of a 18Cr-ODS steel in supercritical water, Corrosion Science 65 (2012) 209–213
China
Paper
2014
Guangming Zhang, Zhangjian Zhou, Hongying Sun, Lei Zou, Man Wang, Shaofu Li, Hot deformation behavior and processing map of a 9Cr ferritic/martensitic ODS steel Journal of Nuclear Materials 455 (2014) 139–144
China
Paper
2012
Helong Hu, Zhangjian Zhou, et al, Study of the corrosion behavior of a 18Cr-oxide dispersion strengthened steel in supercritical water, Corrosion Science 65 (2012) 209–213
Germany
Paper
2012
Heintze C, Hernández-Mayoral M, Ulbricht A, Bergner F, Shariq A, Weissg?rber T, Frielinghaus H. Nanoscale characterization of ODS Fe–9% Cr model alloys compacted by spark plasma sintering. Journal of Nuclear Materials. 2012 Sep 1;428(1-3):139-46.
Japan, Germany
Paper
2012
S. Takaya, T. Furukawa, G. Müller, A. Heinzel, A. Jianu, A. Weisenburger, K. Aoto, M. Inoue, T. Okuda, F. Abe, S. Ohnuki, T. Fujisawa, A. Kimura, "Al-containing ODS steels with improved corrosion resistance to liquid lead–bismuth", Journal of Nuclear Materials, 428 (1-3) (2012) 125-130.