Zobrazeno 1 - 10
of 57
pro vyhledávání: '"S. Gonderman"'
Autor:
G. Sinclair, T. Abrams, S. Bringuier, D.M. Thomas, L. Holland, S. Gonderman, J.H. Yu, R.P. Doerner
Publikováno v:
Nuclear Materials and Energy, Vol 26, Iss , Pp 100939- (2021)
Silicon carbide (SiC) may be a viable option for future plasma-facing components (PFCs) due to its low hydrogenic diffusivity, high temperature strength, and mechanical resilience to neutron damage (Causey et al., 1978). The erosion and retention pro
Externí odkaz:
https://doaj.org/article/f15b4d397d85489bab1fd023a2cf3cbe
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 346-352 (2017)
The selection of tungsten (W) as a divertor material in ITER is based on its high melting point, low erosion, and strong mechanical properties. However, continued investigation has shown W to undergo severe morphology changes in fusion-like condition
Externí odkaz:
https://doaj.org/article/e0618ee6ea734745ab0509cbadd4a519
Autor:
Robert Wilcox, Dmitry Rudakov, S. Gonderman, Stefan Bringuier, Tyler Abrams, Daniel Thomas, L. Holland, G. Sinclair, Filippo Scotti, Ezekial A Unterberg
Silicon carbide (SiC) represents a promising but largely untested plasma-facing material (PFM) for next-step fusion devices. In this work, an analytic mixed-material erosion model is developed by calculating the physical (via SDTrimSP) and chemical (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::81b7097bb988f1dfc1c3a24e6ba276af
http://arxiv.org/abs/2104.04083
http://arxiv.org/abs/2104.04083
Autor:
Stefan Bringuier, Tyler Abrams, L. Holland, J.H. Yu, S. Gonderman, R.P. Doerner, Daniel Thomas, G. Sinclair
Publikováno v:
Nuclear Materials and Energy, Vol 26, Iss, Pp 100939-(2021)
Silicon carbide (SiC) may be a viable option for future plasma-facing components (PFCs) due to its low hydrogenic diffusivity, high temperature strength, and mechanical resilience to neutron damage (Causey et al., 1978). The erosion and retention pro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::83ff98ec110c9b09b6964e960039c4cc
http://www.sciencedirect.com/science/article/pii/S2352179121000326
http://www.sciencedirect.com/science/article/pii/S2352179121000326
Publikováno v:
Journal of Nuclear Materials. 508:26-32
Mitigation of transient plasma events in a future fusion device is necessary to minimize thermal damage on surrounding plasma facing components (PFCs). Intense heat loading caused by an edge-localized mode (ELM) can lead to melting and splashing of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0c7b4f8ebb60287ca77519a2616c5876
https://doi.org/10.1016/j.jnucmat.2018.05.035
https://doi.org/10.1016/j.jnucmat.2018.05.035
Publikováno v:
Journal of Nuclear Materials. 504:1-7
Compared to tungsten (W), tantalum (Ta) has shown superior resistance to helium (He)-induced surface morphology changes under fusion-relevant irradiation conditions. However, Ta is also expected to have a stronger interaction with hydrogen isotopes,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::45197fd4173853e9204de6e924025e3b
https://doi.org/10.1016/j.jnucmat.2018.03.023
https://doi.org/10.1016/j.jnucmat.2018.03.023
Akademický článek
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Publikováno v:
Journal of Nuclear Materials. 491:199-205
Currently, tungsten remains the best candidate for plasma-facing components (PFCs) for future fusion devices because of its high melting point, low erosion, and strong mechanical properties. However, continued investigation has shown tungsten to unde
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::733e52f2eaf9f301c1884312c8b85994
https://doi.org/10.1016/j.jnucmat.2017.05.009
https://doi.org/10.1016/j.jnucmat.2017.05.009
Autor:
Tyler Abrams, Megan E. Goodland, Christian Zuber, Martin Frieß, Markus T. Koller, J.W. Davis, S. Gonderman, Georg Herdrich
Publikováno v:
Nuclear Materials and Energy, Vol 20, Iss, Pp-(2019)
Silicon Carbide (SiC) is a low Z material discussed as an alternative to graphite for fusion devices. The retention of hydrogenous species is an important plasma-surface interaction property. Deuterium was implanted into SiC, SiCf/SiC, Cf/C-SiC and S
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a448f58e657f36c5b9bd7f1ba968d0aa
https://elib.dlr.de/133177/
https://elib.dlr.de/133177/
Publikováno v:
Journal of Nuclear Materials. 478:287-294
We report on the role of carbon (C) impurities, in molybdenum (Mo) fuzz evolutions on Mo surface during 100 eV He + ion irradiations. In this study we considered 0.01, 0.05, and 0.5% C + ion impurities in He + ion irradiations. For introducing such t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::689a7c6a05a8fe81f66364e711484d3a
https://doi.org/10.1016/j.jnucmat.2016.06.026
https://doi.org/10.1016/j.jnucmat.2016.06.026