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

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Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation. / Rieth, Michael; Simondon, Esther; Pintsuk, Gerald; Aiello, G.; Aiello, J.; Terentyev, Dmitry; Puype, Athina; Cristalli, C.; Pilloni, L.; Tassa, O.; Klimenkov, Michail; Schneider, Hans-Christian; Fernandez, P.; Gräning, T.; Chen , X.; Bhattacharya, A.; Reed, Joel W.; Geringer, J.W.; Sokolov, Mikhail; Katoh, Y.; Snead, L.

In: Fusion Engineering & Design, Vol. 168, 112645, 15.05.2021, p. 1-11.

Research output: Contribution to journalArticlepeer-review

Harvard

Rieth, M, Simondon, E, Pintsuk, G, Aiello, G, Aiello, J, Terentyev, D, Puype, A, Cristalli, C, Pilloni, L, Tassa, O, Klimenkov, M, Schneider, H-C, Fernandez, P, Gräning, T, Chen , X, Bhattacharya, A, Reed, JW, Geringer, JW, Sokolov, M, Katoh, Y & Snead, L 2021, 'Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation', Fusion Engineering & Design, vol. 168, 112645, pp. 1-11. https://doi.org/10.1016/j.fusengdes.2021.112645

APA

Rieth, M., Simondon, E., Pintsuk, G., Aiello, G., Aiello, J., Terentyev, D., Puype, A., Cristalli, C., Pilloni, L., Tassa, O., Klimenkov, M., Schneider, H-C., Fernandez, P., Gräning, T., Chen , X., Bhattacharya, A., Reed, J. W., Geringer, J. W., Sokolov, M., ... Snead, L. (2021). Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation. Fusion Engineering & Design, 168, 1-11. [112645]. https://doi.org/10.1016/j.fusengdes.2021.112645

Author

Rieth, Michael ; Simondon, Esther ; Pintsuk, Gerald ; Aiello, G. ; Aiello, J. ; Terentyev, Dmitry ; Puype, Athina ; Cristalli, C. ; Pilloni, L. ; Tassa, O. ; Klimenkov, Michail ; Schneider, Hans-Christian ; Fernandez, P. ; Gräning, T. ; Chen , X. ; Bhattacharya, A. ; Reed, Joel W. ; Geringer, J.W. ; Sokolov, Mikhail ; Katoh, Y. ; Snead, L. / Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation. In: Fusion Engineering & Design. 2021 ; Vol. 168. pp. 1-11.

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@article{3d51ab86341149af8a552d053014da7e,
title = "Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation",
abstract = "Presently available data on neutron irradiation damage raise doubts on the feasibility of using EUROFER97 steel for a water-cooled starter blanket in a DEMO reactor, since the ductile-to-brittle transition temperature (DBTT) increases significantly for irradiation temperatures below 350.C. The additional DBTT shift caused by H and He transmutation can only be estimated based on very few results with isotopically tailored EUROFER97 steel. Conservative calculations show that the DBTT of EUROFER97 steel could exceed the operating temperature in water-cooled starter blankets within a relatively short time period. This paper presents results from a EUROfusion funded irradiation campaign that was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. The paper compares ten newly developed reduced activation ferritic-martensitic (RAFM) steels irradiated to a nominal dose of 2.5 dpa at 300.C. The post-irradiation experiments using Small Specimen Test Technology included hardness, tensile, and fracture mechanics tests combined with fractography and microstructure analysis are presented. Results show that micro-alloying EUROFER97-type steels influenced the mechanical properties but a dominating impact on irradiation damage resistance could not be identified. In contrast, specific thermo-mechanical treatments lead to better DBTT behavior. Discussion about irradiation response to heat treatment conditions is also given. Despite requiring data also at high dpa values, the results indicate that with these modified materials an increased lifetime and potentially also an increased operating temperature window can be achieved compared to EUROFER97.",
keywords = "EUROFER97, Thermo-mechanical treatment, Neutron irradiation, Post irradiation examination, Embrittlement, Fracture toughness",
author = "Michael Rieth and Esther Simondon and Gerald Pintsuk and G. Aiello and J. Aiello and Dmitry Terentyev and Athina Puype and C. Cristalli and L. Pilloni and O. Tassa and Michail Klimenkov and Hans-Christian Schneider and P. Fernandez and T. Gr{\"a}ning and X. Chen and A. Bhattacharya and Reed, {Joel W.} and J.W. Geringer and Mikhail Sokolov and Y. Katoh and L. Snead",
note = "Score=10",
year = "2021",
month = may,
day = "15",
doi = "10.1016/j.fusengdes.2021.112645",
language = "English",
volume = "168",
pages = "1--11",
journal = "Fusion Engineering & Design",
issn = "0920-3796",
publisher = "Elsevier",

}

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TY - JOUR

T1 - Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation

AU - Rieth, Michael

AU - Simondon, Esther

AU - Pintsuk, Gerald

AU - Aiello, G.

AU - Aiello, J.

AU - Terentyev, Dmitry

AU - Puype, Athina

AU - Cristalli, C.

AU - Pilloni, L.

AU - Tassa, O.

AU - Klimenkov, Michail

AU - Schneider, Hans-Christian

AU - Fernandez, P.

AU - Gräning, T.

AU - Chen , X.

AU - Bhattacharya, A.

AU - Reed, Joel W.

AU - Geringer, J.W.

AU - Sokolov, Mikhail

AU - Katoh, Y.

AU - Snead, L.

N1 - Score=10

PY - 2021/5/15

Y1 - 2021/5/15

N2 - Presently available data on neutron irradiation damage raise doubts on the feasibility of using EUROFER97 steel for a water-cooled starter blanket in a DEMO reactor, since the ductile-to-brittle transition temperature (DBTT) increases significantly for irradiation temperatures below 350.C. The additional DBTT shift caused by H and He transmutation can only be estimated based on very few results with isotopically tailored EUROFER97 steel. Conservative calculations show that the DBTT of EUROFER97 steel could exceed the operating temperature in water-cooled starter blankets within a relatively short time period. This paper presents results from a EUROfusion funded irradiation campaign that was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. The paper compares ten newly developed reduced activation ferritic-martensitic (RAFM) steels irradiated to a nominal dose of 2.5 dpa at 300.C. The post-irradiation experiments using Small Specimen Test Technology included hardness, tensile, and fracture mechanics tests combined with fractography and microstructure analysis are presented. Results show that micro-alloying EUROFER97-type steels influenced the mechanical properties but a dominating impact on irradiation damage resistance could not be identified. In contrast, specific thermo-mechanical treatments lead to better DBTT behavior. Discussion about irradiation response to heat treatment conditions is also given. Despite requiring data also at high dpa values, the results indicate that with these modified materials an increased lifetime and potentially also an increased operating temperature window can be achieved compared to EUROFER97.

AB - Presently available data on neutron irradiation damage raise doubts on the feasibility of using EUROFER97 steel for a water-cooled starter blanket in a DEMO reactor, since the ductile-to-brittle transition temperature (DBTT) increases significantly for irradiation temperatures below 350.C. The additional DBTT shift caused by H and He transmutation can only be estimated based on very few results with isotopically tailored EUROFER97 steel. Conservative calculations show that the DBTT of EUROFER97 steel could exceed the operating temperature in water-cooled starter blankets within a relatively short time period. This paper presents results from a EUROfusion funded irradiation campaign that was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. The paper compares ten newly developed reduced activation ferritic-martensitic (RAFM) steels irradiated to a nominal dose of 2.5 dpa at 300.C. The post-irradiation experiments using Small Specimen Test Technology included hardness, tensile, and fracture mechanics tests combined with fractography and microstructure analysis are presented. Results show that micro-alloying EUROFER97-type steels influenced the mechanical properties but a dominating impact on irradiation damage resistance could not be identified. In contrast, specific thermo-mechanical treatments lead to better DBTT behavior. Discussion about irradiation response to heat treatment conditions is also given. Despite requiring data also at high dpa values, the results indicate that with these modified materials an increased lifetime and potentially also an increased operating temperature window can be achieved compared to EUROFER97.

KW - EUROFER97

KW - Thermo-mechanical treatment

KW - Neutron irradiation

KW - Post irradiation examination

KW - Embrittlement

KW - Fracture toughness

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/46402274

U2 - 10.1016/j.fusengdes.2021.112645

DO - 10.1016/j.fusengdes.2021.112645

M3 - Article

VL - 168

SP - 1

EP - 11

JO - Fusion Engineering & Design

JF - Fusion Engineering & Design

SN - 0920-3796

M1 - 112645

ER -

ID: 7277059