Critical questions in materials science and engineering for successful development of fusion power

Bloom, E.E.; Busby, Jeremy T.; Duty, Chad; Maziasz, P.J.; McGreevy, Timothy; Nelson, B.; Pint, Bruce A.; Tortorelli, P.F.; Zinkle, S.J.

doi:10.1016/j.jnucmat.2007.02.007

Cited by 73 publications

(38 citation statements)

References 38 publications

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“…Radiologically unfavourable alloying elements such as Mo, Nb and Ni were replaced with W and Ta. As a result of an integrated European research and test program [4][5][6][7], taking into account experience from R&D programs in Japan and US [8][9][10], a 9% CrWVTa alloy called EUROFER-97 was specified with W, V, Ta content in the range of 1.0-1.2%, 0.15-0.25% and 0.10-0.14%, respectively.…”

Section: Alloy Selection and Industrial Heat Productionmentioning

confidence: 99%

Structural materials for DEMO: The EU development, strategy, testing and modelling

Lässer¹,

Baluc

Boutard³

et al. 2007

Fusion Engineering and Design

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Section: Alloy Selection and Industrial Heat Productionmentioning

confidence: 99%

Structural materials for DEMO: The EU development, strategy, testing and modelling

Lässer¹,

Baluc

Boutard³

et al. 2007

Fusion Engineering and Design

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“…1 In particular, future fusion reactors will produce a much larger amount of both He and H as compared to fission reactors, hence the microstructure of the structural materials used in fusion reactors will be much more sensitive to interactions with He defects. 2,3 In terms of radiation damage, the production of helium through (n, a) transmutation reactions causes both microstructure evolution and drastic property changes in the first-wall and blanket structural materials of fusion reactors. The production of single helium atoms and small He clusters in the metal lattice is inherently a problem that occurs at the nanoscale.…”

Section: Introductionmentioning

confidence: 99%

Binding of HenV clusters to α-Fe grain boundaries

Tschopp

Gao

Solanki³

2014

Journal of Applied Physics

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Articles you may be interested inBinding energetics of substitutional and interstitial helium and di-helium defects with grain boundary structure in - The objective of this research is to explore the formation/binding energetics and length scales associated with the interaction between He n V clusters and grain boundaries in bcc a-Fe. In this work, we calculated formation/binding energies for 1-8 He atoms in a monovacancy at all potential grain boundary (GB) sites within 15 Å of the ten grain boundaries selected (122106 simulations total). The present results provide detailed information about the interaction energies and length scales of 1-8 He atoms with grain boundaries for the structures examined. A number of interesting new findings emerge from the present study. First, the R3(112) "twin" GB has significantly lower binding energies for all He n V clusters than all other boundaries in this study. For all grain boundary sites, the effect of the local environment surrounding each site on the He n V formation and binding energies decreases with an increasing number of He atoms in the He n V cluster. Based on the calculated dataset, we formulated a model to capture the evolution of the formation and binding energy of He n V clusters as a function of distance from the GB center, utilizing only constants related to the maximum binding energy and the length scale. V C 2014 AIP Publishing LLC.

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“…However, several key issues remain unsolved that include incomplete understanding of the effect of irradiation on low-temperature fracture properties, the role of fusionrelevant helium and hydrogen transmutation gases on the deformation and fracture of irradiated materials, and mechanisms of swelling suppression in ODS steels [4,5]. Since no prototype fusion reactors currently exist, it is difficult to directly evaluate the high-energy neutron damage environment expected to prevail in the first wall of a fusion reactor.…”

Section: Introductionmentioning

confidence: 99%

HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance

Hsiung

Fluss

Tumey

et al. 2011

Journal of Nuclear Materials

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Crystal and interfacial structures of oxide nanoparticles and radiation damage in 16Cr-4.5Al-0.3Ti-2W-0.37 Y 2 O 3 ODS ferritic steel have been examined using high-resolution transmission electron microscopy (HRTEM) techniques. Oxide nanoparticles with a complex-oxide core and an amorphous shell were frequently observed. The crystal structure of complex-oxide core is identified to be mainly monoclinic Y 4 Al 2 O 9 (YAM) oxide compound. Orientation relationships between the oxide and the matrix are found to be dependent on the particle size. Large particles (> 20 nm) tend to be incoherent and have a spherical shape, whereas small particles (< 10 nm) tend to be coherent or semi-coherent and have a faceted interface. The observations of partially amorphous nanoparticles and multiple crystalline domains formed within a nanoparticle lead us to propose a three-stage mechanism to rationalize the formation of oxide nanoparticles containing core/shell structures in as-fabricated ODS steels. Effects of nanoparticle size and density on cavity formation induced by (Fe 8+ + He + ) dual-beam irradiation are briefly addressed.

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Critical questions in materials science and engineering for successful development of fusion power

Cited by 73 publications

References 38 publications

Structural materials for DEMO: The EU development, strategy, testing and modelling

Structural materials for DEMO: The EU development, strategy, testing and modelling

Binding of HenV clusters to α-Fe grain boundaries

HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance

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