Assessment and selection of materials for ITER in-vessel components

Kalinin, G.; Barabash, V.; Cardella, A.; Dietz, J.; Ioki, K.; Matera, R.; Santoro, R.T.; Tivey, R.

doi:10.1016/s0022-3115(00)00305-6

Cited by 127 publications

(50 citation statements)

References 15 publications

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“…As for commercial austenitic steels, we have taken: i) SS 304, nominal 18Cr-10Ni-2Mn-0.08C, which was proposed for HYLIFE-II 3,4 , and ii) a specific SS316 selected as structural material in the ITER project, nominal 18Cr-12Ni-2Mn-2Mo-0.02C 5,6 . Regarding commercial ferritic/martensitic steels, we investigate the activation of HT9 and mod.9Cr-1Mo (T91), steels considered for different nuclear -fusion and fast reactors-applications 7,8 .…”

Section: Iia Candidate Materials: Commercial and Reduced Activationmentioning

confidence: 99%

“…The HiPER 4a reaction chamber will deal with a neutron yield environment that could reach up to 1.2·10 5 MJ/yr. This represents two orders of magnitude higher compared to NIF 1 , the inertial fusion experimental facility that could be considered most similar to HiPER 4a.…”

Section: Introductionmentioning

confidence: 99%

“…Steels, which are widely used in power plants and other industries under demanding operational requirements, have been considered from the beginnings of fusion technology as one of the most promising candidate structural materials for inertial and magnetic fusion energy (IFE and MFE) reactor chambers. [2][3][4][5][6][7][8][9][10][11][12][13] As continuation of the ARIES-IFE study 12 , an extensive activation analysis in selecting steels for the HYLIFE-II chamber qualifying for successful waste management was performed 13 . Different commercial austenitic and Cr-Mo ferritic/martensitic steels, as well as some MFE-intended reduced-activation steels were studied.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Sanz

Juárez

Ognissanto

et al. 2011

Fusion Science and Technology

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Section: Iia Candidate Materials: Commercial and Reduced Activationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Sanz

Juárez

Ognissanto

et al. 2011

Fusion Science and Technology

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“…This is based on their excellent thermal shock resistance [1,2], absence of melting in comparison with metals and ability to retain the strength up to high temperatures [3,4]. These are desirable properties for the strike point area of the ITER divertor during the start-up phase without tritium [5][6][7] as well as for the divertor of WENDELSTEIN 7-X [8,9].…”

Section: Mechanical and Thermo-physical Characterization Of 3-directimentioning

confidence: 99%

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Pintsuk

Compan

Koppitz

et al. 2009

Fusion Engineering and Design

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Carbon fiber composites (CFCs) are the first choice as plasma facing materials for the strike points of divertor targets for future nuclear fusion devices like WENDELSTEIN 7-X and ITER. For the application in these facilities several potential European 3D-CFCs were compared and qualified: 1) four material batches of NB31 produced by Snecma Propulsion Solide (SNECMA); 2) NB41, SNECMA, the upgraded version of NB31; 3) N31, SNECMA, which is densified by chemical vapor infiltration (CVI) instead of a final liquid pitch infiltration characteristic for NB31; 4) a new developmental 3D-CFC produced by DUNLOP.The characterization of the composites is comprised of thermo-physical measurements and tensile tests. The results are correlated to density and microstructure and summarized as follows: 1) NB41 provides the highest thermal conductivity in the ex-pitch direction of ~375 W/m.K at room temperature; 2) all material grades are, due to their heterogeneity, characterized by a relatively large scatter of mechanical properties; 3) the different densification process for N31 in comparison to NB31 has no influence on the material properties; 4) NB41 provides in all 3 directions a comparably high tensile strength with an average in the ex-pitch direction of ~220 MPa; 5) the 3D-

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“…The recent conceptual designs of a fusion reactor, both confinements as magnetic inertial [2] consider tungsten (W) as one of the functional materials [3][4][5], candidate to be part of several engineering units, in particular the first wall or first containment barrier, the divertor [5,6], subjected to extreme conditions, temperatures and irradiation, even higher than those in a fission reactor in terms of fluxes, spectrum hardness and number of source terms (neutrons, gamma, H, H 2 , 4 He, 3 He). Of all metals and alloys, tungsten has the highest melting and boiling point (PF-3,422 °C, PE-5,930 °C), exhibits high hardness and good heat…”

mentioning

confidence: 99%

Behavior of Hydrogen and Nitrogen in Tungsten, as Divertor Wall of a Fusion Reactor

Beneitez¹,

Gervasoni²,

Furnari³

2018

JEPE

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Abstract:The analysis of the interaction of hydrogen, nitrogen (and their isotopes) with tungsten is important, since this material is a strong candidate to form the first wall of fusion reactors for both magnetic and inertial confinement, and these atoms have a very sensitive (desired and unwanted) interaction with it. For this purpose, we study the effects and electronic state densities of atomic hydrogen and nitrogen in pure tungsten, in order to analyze some important properties such as the density of states of the system. Focusing on this application, this work is a preliminary study of the behavior of atoms of hydrogen and nitrogen, on a surface of tungsten on the three sites of the cell: top, hollow and bridge. We use a program simulation based on the DFT (density functional theory) implemented in the Open-Source Code Quantum Espresso, in order to obtain the adsorption energy and the density of states of the systems.

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Assessment and selection of materials for ITER in-vessel components

Cited by 127 publications

References 15 publications

Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER

Behavior of Hydrogen and Nitrogen in Tungsten, as Divertor Wall of a Fusion Reactor

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