Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation

Rieth, M.; Simondon, E.; Pintsuk, G.; Aiello, G.; Henry, J.; Terentyev, D.; Puype, Athina; Cristalli, C.; Pilloni, L.; Tassa, O.; Klimenkov, M.; Schneider, Holger; Fernández, P.; Gräning, Tim; Chen, Xin; Bhattacharya, Arunodaya; Reed, Jordan; Geringer, Josina W.; Sokolov, Mikhail A.; Katoh, Yutai; Snead, L.L.

doi:10.1016/j.fusengdes.2021.112645

Cited by 15 publications

(10 citation statements)

References 19 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, the variation of irradiated σ YS at lower T irr and up to ∼300 • C-350 • C is relatively gradual as compared to the rapid recovery of σ YS when T irr ⩾ 350 • C. Hardening increases sharply with neutron doses as low as ∼0.1-0.2 dpa, and continues to increase up to at least ∼10-15 dpa in RAFM steels (figure 3). By ITER-relevant conditions of 2.5-3 dpa around 300 • C, RAFM steels can harden by as much as 50%-70% (∼by 350-400 MPa) compared to their initial σ YS [62,66]. After ∼15 dpa, hardening in RAFM steels such as Eurofer97 or F82H saturates and remains nearly constant up to very high doses exceeding >50-70 dpa, as shown in figure 3.…”

Section: Low Temperature Hardening-embrittlement (Lthe) In Rafm and O...mentioning

confidence: 93%

“…The chief concern with current generation (Gen-I) RAFM steels is the projected very narrow operational temperature window of ∼350 • C-550 • C in fusion environments [45,54,58]. The lower temperature limit is imposed due to the irradiation-induced low-temperature hardening embrittlement (LTHE) phenomenon, resulting in an increase of yield and tensile strength, loss of tensile elongation and severe loss of fracture toughness (FT) with an increase in ductile-to-brittle transition temperature (DBTT) for neutron doses as low as ∼0.1-15 dpa and irradiation temperatures (T irr ) ⩽ ∼350 • C [38,[60][61][62][63][64][65][66]. LTHE is a major challenge in reactor design, particularly for the water-cooled DEMO blanket concepts, where operating temperatures in the range of ∼280 • C-350 • C are expected [67].…”

Section: Major Challenges For Rafm Steelsmentioning

confidence: 99%

“…It is generally observed that harder under-tempered RAFM steels (room temperature σ YS > 800-900 MPa), being designed to optimise high-temperature strength [26,62,144], offer a relatively low percentage increase in σ YS after neutron irradiation as compared to those produced by conventional heat treatments or by over-tempering [62,66]. The harder steels also seem to show relatively less degradation of the tensile elongation due to irradiation.…”

Section: Low Temperature Hardening-embrittlement (Lthe) In Rafm and O...mentioning

confidence: 99%

“…FT improvements of RAFM steels by TMTs combined with minor alloying chemistries has been attempted, for example in the mod3 variant of F82H [20] and some variants of Eurofer97 [62]. While the mod3 variants showed improved mechanical properties in the non-irradiated condition and seem to show slightly better FT properties after high dose neutron irradiations [100], the variants of Eurofer97 fabricated with TMTs showed only modest improvements in the neutron irradiated FT and tensile properties [64,66].…”

Section: Strategies To Improve Rafm Steel Performance For Fusion Appl...mentioning

confidence: 99%

See 3 more Smart Citations

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

et al. 2022

View full text Add to dashboard Cite

Reduced activation ferritic-martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. Performance of these steels will deteriorate in-service due to neutron damage and transmutation-induced gases like helium/hydrogen at elevated operating temperatures. Here, after highlighting the operating conditions of fusion reactor concepts and a brief overview, the major irradiation-induced degradation challenges associated with RAFM/ODS steels are discussed. Their long-term degradation scenarios such as (i) low temperature hardening-embrittlement (LTHE) - including dose-temperature dependent yield stress, tensile elongations, necking ductility, test temperature effect on hardening, Charpy impact ductile to brittle transition temperature and fracture toughness, (ii) inter-mediate temperature cavity swelling, (iii) the effect of helium on LTHE and cavity swelling, (iv) irradiation creep and (v) tritium management issues are reviewed. The potential causes of LTHE are discussed that highlights need for advanced characterization techniques. Mechanical properties including tensile/Charpy impact of RAFM and ODS steels are compared to show that current generation of ODS steels also suffer from LTHE, and they can show irradiation hardening up to high temperatures, ~400-500 °C. To minimize this, future ODS steel development for FW/B specific application should target materials with lower Cr concentration (to minimize α’) and minimize other elements that could form embrittling phases under irradiation. RAFM steel designing activities targeting improvements in creep and LTHE are reviewed. The need to better understand synergistic effects of helium on thermo-mechanical properties in the entire temperature range of FW/B is highlighted. Because fusion operating conditions will be complex including stresses due to magnetic field, primary loads like coolant pressure, secondary loads from thermal gradients, and due to spatial variation in damage levels and gas production rates, an experimentally validated multi-scale modelling approach is suggested as a pathway to future reactor component designing such as for the fusion neutron science facility

show abstract

Section: Low Temperature Hardening-embrittlement (Lthe) In Rafm and O...mentioning

confidence: 93%

Section: Major Challenges For Rafm Steelsmentioning

confidence: 99%

Section: Low Temperature Hardening-embrittlement (Lthe) In Rafm and O...mentioning

confidence: 99%

Section: Strategies To Improve Rafm Steel Performance For Fusion Appl...mentioning

confidence: 99%

See 2 more Smart Citations

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

et al. 2022

View full text Add to dashboard Cite

show abstract

“…(1) use of oxide-dispersion strengthened (ODS) steels [93,[293][294][295][296][297], with a target of 700 • C or beyond as upper limit operating temperature [93,293,294]; (2) composition-tuning and application of suitable thermal-mechanical treatments (TMT), in a conventional metallurgy framework, with a target upper temperature limit of 650 • C [294,[298][299][300][301]. Metallurgical techniques of the second type may also help to control radiation embrittlement below 350 • C [302].…”

Section: Annex 3-pathways To Nuclear Materials Improvement For Next G...mentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

View full text Add to dashboard Cite

Nuclear energy is presently the single major low-carbon electricity source in Europe and is overall expected to maintain (perhaps eventually even increase) its current installed power from now to 2045. Long-term operation (LTO) is a reality in essentially all nuclear European countries, even when planning to phase out. New builds are planned. Moreover, several European countries, including non-nuclear or phasing out ones, have interests in next generation nuclear systems. In this framework, materials and material science play a crucial role towards safer, more efficient, more economical and overall more sustainable nuclear energy. This paper proposes a research agenda that combines modern digital technologies with materials science practices to pursue a change of paradigm that promotes innovation, equally serving the different nuclear energy interests and positions throughout Europe. This paper chooses to overview structural and fuel materials used in current generation reactors, as well as their wider spectrum for next generation reactors, summarising the relevant issues. Next, it describes the materials science approaches that are common to any nuclear materials (including classes that are not addressed here, such as concrete, polymers and functional materials), identifying for each of them a research agenda goal. It is concluded that among these goals are the development of structured materials qualification test-beds and materials acceleration platforms (MAPs) for materials that operate under harsh conditions. Another goal is the development of multi-parameter-based approaches for materials health monitoring based on different non-destructive examination and testing (NDE&T) techniques. Hybrid models that suitably combine physics-based and data-driven approaches for materials behaviour prediction can valuably support these developments, together with the creation and population of a centralised, “smart” database for nuclear materials.

show abstract

Review on development of reduced activated ferritic/martensitic steel for fusion reactor

Qiu

Zhan

Cao³

et al. 2022

J. Iron Steel Res. Int.

View full text Add to dashboard Cite

Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation

Cited by 15 publications

References 19 publications

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Review on development of reduced activated ferritic/martensitic steel for fusion reactor

Contact Info

Product

Resources

About