| Issue |
EPJ Nuclear Sci. Technol.
Volume 8, 2022
Euratom Research and Training in 2022: challenges, achievements and future perspectives
|
|
|---|---|---|
| Article Number | 42 | |
| Number of page(s) | 9 | |
| Section | Part 1: Safety research and training of reactor systems | |
| DOI | https://doi.org/10.1051/epjn/2022033 | |
| Published online | 15 December 2022 | |
- MICRIN+project, state-of-the-art report on surface requirements and practises for NPP primary components, Deliverable 1 [Google Scholar]
- Materials reliability Program: Topical report for primary water stress corrosion cracking mitigation by surface stress improvement (MRP-335 Revision 3) [Google Scholar]
- B.M. Gordon, Corrosion and corrosion control in light water reactors, JOM 65, 1043 (2013) [CrossRef] [Google Scholar]
- J.M. Zhou, et al., Analysis of subsurface microstructure and residual stresses in machined Inconel 718 with PCBN and Al2O3-SiCw tools, Procedia CIRP 13, 150 (2014) [CrossRef] [Google Scholar]
- T. Ozel, D. Ulutan, Prediction of machining induced residual stresses in turning of titanium and nickel based alloys with experiments and finite element simulations, CIRP Annals 61, 547 (2012) [CrossRef] [Google Scholar]
- X. Wu, et al., Microstructure and evolution of mechanically-induced ultrafine grain in surface layer of AL-alloy subjected to USSP, Acta Mater. 50, 2075 (2002) [CrossRef] [Google Scholar]
- R. M’Saoubi, et al., Surface integrity analysis of machined Inconel 718 over multiple length scales, CIRP Annals 61, 99 (2012) [CrossRef] [Google Scholar]
- V. Bushlya, et al., Characterization of white layer generated when turning aged Inconel 718, Procedia Engineering 19, 60 (2011) [CrossRef] [Google Scholar]
- S. Berger, et al., Mitigation of crack initiation in LWRs (MICRIN+), in European Corrosion Congress, EUROCORR 2016 (2016) [Google Scholar]
- A. Hojná, Acceleration test matrix for SCC prediction, in NACE Milano Italia Section, Corrosion Protection in Oil & Refinery Industry (Genova, 2016) [Google Scholar]
- ASME, Section III division 1, rules for construction of nuclear power plant components, in Boiler and Pressure Vessel Code (ASME International (BPVC), New York, 2021) [Google Scholar]
- AFCEN, RCC-M design and construction rules for mechanical components of PWR nuclear Islands. Section I (2018) [Google Scholar]
- JSME, Code for nuclear power generation facilities – rules on design and construction for nuclear power plants-, division 1 Rules on light water reactor, JSME S NC1-2012 (2012) [Google Scholar]
- CEN, BS EN 13445–3:2014+A2:2016: Unfired pressure vessels – part 3: Design (2016) [Google Scholar]
- ONRC, NUREG/CR-6909, Effect of LWR water environments on the fatigue life of reactor materials, revision 1 (Washington, 2018) [Google Scholar]
- EPRI, Environmentally Assisted Fatigue (EAF) Knowledge Gap Analysis: Update and Revision of the EAF Knowledge Gaps, 3002013214 (Palo Alto, 2018) [Google Scholar]
- A.G. McLennan, A. Morley, S. Cuvilliez, Further evidence of margin for environmetnal effects, termed fen-threshold, in the ASME section III design fatigue curve for austenitic stainless steels through the interaction between the PWR environment and surface finish, in Proceedings of the ASME 2020 Pressure Vessels & Piping Conference PVP2020 (2020) [Google Scholar]
- T. Métais et al., Explicit quantification of the interaction between the PWR environment and component surface finish in environmental fatigue evaluation methods for austenitic stainless steels, in Proceedings of the ASME 2018 Pressure Vessels and Piping Conference PVP2018 (Prague, 2018) [Google Scholar]
- C. Currie et al., Further validation of the Strain-Life Weighted (SNW) fen method for plant realistic strain and temperature waveforms, in Proceedings of the ASME 2018 Pressure Vessels and Piping Conference PVP2018 (Prague, 2018) [Google Scholar]
- J. Colin, A. Fatemi, S. Taheri, Fatigue behaviour of stainless steel 304L including strain hardening, prestraining, and mean stress effects, J. Eng. Mater. Technol. 132, 021008 (2010). [CrossRef] [Google Scholar]
- A. Fissolo, J.M. Stelmaszyk, A first investigation on cumulative fatigue life for a type 304-L stainless steel used for pressure water reactor PVP2009-77156, in Proceedings of the ASME 2009 Pressure Vessels and Piping Division Conference PVP2009 (Prague, 2009) [Google Scholar]
- S. Asada, Y. Nomura, Development of new design fatigue curves in Japan – treatment of variable loading amplitude effect-, PVP2021-60418, in Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 (2021) [Google Scholar]
- B. Howe, et al., Development of a robust procedure for the evaluation of striation spacings in low cycle fatigue specimens tested in a simulated PWR environment, in Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 (2022) [Google Scholar]
- FRACTESUS official website. Available from: https://fractesus-h2020.eu/ [Google Scholar]
- ASTM, ASTM E1921 – standard test method for determination of reference temperature, T0, for ferritic steels in the transition range (2021) [Google Scholar]
- T. Brynk, et al., FRACTESUS project: General framework of materials selection and testing processes, in PVP2021-61906 (2021) [Google Scholar]
- M. Yamamoto, et al., in International Round Robin Test on Master Curve Reference Temperature Evaluation Utilizing Miniature C(T) Specimen, edited by M. Sokolov, E. Lucon (ASTM International, West Conshohocken, PA, 2014), pp. 1–17 [Google Scholar]
- M.A. Sokolov, The fracture toughness evaluation of Mini-CT specimen test results of the irradiated midland RPV beltline material, ORNL/TM-2018/509 (2018) [Google Scholar]
- S. Cicero, et al., Fracture mechanics testing of irradiated RPV steels by means of sub-sized specimens: FRACTESUS project, Struct. Integr. Proc. 28 (2020) [Google Scholar]
- P. Arffman, Test matrix of FRACTESUS, Deliverable D2.1 of EU project No. 900014 FRACTESUS (2021) [Google Scholar]
- T. Brynk, et al., FRACTESUS project: Final selection of RPV materials for unirradiated and irradiated round robins PVP2022-83871 (to be published) [Google Scholar]
- E. Altstadt, F. Bergner, M. Houska, Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels, Nucl. Mater. Energy 26, 100918 (2021) [CrossRef] [Google Scholar]
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