Current status and future R&amp;D for reduced-activation ferritic/martensitic steels

Hishinuma, A.; Kohyama, Akira; Klueh, R.L.; Gelles, D.S.; Dietz, W.; Ehrlich, K.

doi:10.1016/s0022-3115(98)00395-x

Cited by 255 publications

(132 citation statements)

References 13 publications

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“…Ferritic/martensitic steels are one of the candidate materials for the vessel of the spallation target [1], and reduced-activation ferritic/martensitic (RAFM) steels, such as Eurofer, are first priority materials of structure for fusion nuclear reactors [2,3]. These systems are desired to operate at relatively high temperatures up to 650 С. RAFM steels possess exceptional thermal conductivity and low thermal expansion among other steels while being strongly resistant to void swelling.…”

Section: Introductionmentioning

confidence: 99%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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Section: Introductionmentioning

confidence: 99%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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“…[1][2][3] The fast neutrons cause displacement damage and produce transmutation products such as He atoms in materials. It is necessary to understand the effects of simultaneous formation of the displacement damage and large amounts of He on the mechanical properties and the microstructures of the steels.…”

Section: Introductionmentioning

confidence: 99%

Heat Treatment Effects on Microstructures and DBTT of F82H Steel Doped with Boron and Nitrogen

Okubo¹,

Wakai²,

Matsukawa³

et al. 2005

Mater. Trans.

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Effects of doping with 60 ppm B and/or 200 ppm N and heat treatments on the microstructures and the ductile-brittle transition temperature (DBTT) have been studied for ferritic/martensitic steel F82H. Prior austenitic grain size of standard F82H decreased from about 120 to 30 mm and also the DBTT decreased by about 50 C when the normalizing temperatures were changed from 1040 to 950 C. In case of F82H doped with B (F82H+B) normalized at 950 C the grain size increased from 30 to 40 mm and the DBTT increased by about 50 C as compared with that of the standard F82H. In case of F82H co-doped with B and N (F82H+B+N) the grain size and DBTT, however, were comparable to each one of the standard F82H. Localization of B and C with the size of a few mm at grain boundaries was observed in the F82H+B by using a time of flightsecondary ion mass spectroscope, but not in the F82H+B+N. The results indicated that the degradation of fracture toughness in F82H+B was caused mainly by the localization of B at the grain boundaries. The DBTT of F82H+B+N steels normalized at the temperatures from 950 to 1040 C was changed from À96 to À73 C, but the prior austenitic grain size remained nearly unchanged. The precipitate size, however, depended on the normalizing temperature. It was shown that the change of DBTT was related to the change in the mean size of the precipitates in the F82H+B+N steels. Keywords: heat treatment, microstructure, ductile-brittle transition temperature, ferritic/martensitic steel, boron and/or nitrogen doping, time of flight-secondary ion mass spectrometry

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“…Actually the use of stainless steel has not been planned for nuclear plants like ITER because of its low thermal conductivity and He embrittlement. The worldwide research for DEMO is actually focused on 8-9 Chrome ferritic/martensitic steels [82][83][84][85][86].…”

Section: Parameter Fusion Fission (Generation Iv) Spallationmentioning

confidence: 99%

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

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Abstract:The choice of materials for the future nuclear fusion reactors is a crucial issue. In the fusion reactors, the combination of very high temperatures, high radiation levels, intense production of transmuting elements and high thermomechanical loads requires very high-performance materials. Erosion of PFCs (Plasma Facing Components) determines their lifetime and generates a source of impurities (i.e., in-vessel tritium and dust inventories), which cool down and dilute the plasma. The resuspension of dust could be a consequences of LOss of Coolant Accidents (LOCA) and LOss of Vacuum Accidents (LOVA) and it can be dangerous because of dust radioactivity, toxicity, and capable of causing an explosion. These characteristics can jeopardize the plant safety and pose a serious threat to the operators. The purpose of this work is to determine the experimental and numerical steeps to develop a numerical model to predict the dust resuspension consequences in case of accidents through a comparison between the experimental results taken from campaigns carried out with STARDUST-U and the numerical simulation developed with CFD codes. The authors in this work will analyze the candidate materials for the future nuclear plants and the consequences of the resuspension of its dust in case of accidents through the experience with STARDUST-U.

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Current status and future R&D for reduced-activation ferritic/martensitic steels

Cited by 255 publications

References 13 publications

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

Heat Treatment Effects on Microstructures and DBTT of F82H Steel Doped with Boron and Nitrogen

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

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