Zobrazeno 1 - 10
of 84
pro vyhledávání: '"Shahram Sharafat"'
Autor:
Alice Ying, Adam Ghoniem, Masashi Shimada, Nasr M. Ghoniem, Brian H Williams, Shahram Sharafat
Publikováno v:
Fusion Engineering and Design. :119-127
A new high-performance cellular solid breeder is presented that has several times the thermal conductivity and is substantially denser compared with sphere-packed breeder beds. The cellular breeder is fabricated using a patented process of melt-infil
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6e9678731b70ba7738b69b5b164160fb
https://doi.org/10.1016/j.fusengdes.2016.03.041
https://doi.org/10.1016/j.fusengdes.2016.03.041
Autor:
Shahram Sharafat, Mohamed A. Abdou, Cyril Courtessole, T. Sketchley, S. Sahu, Sergey Smolentsev
Publikováno v:
Fusion Engineering and Design. 108:7-20
A flow channel insert (FCI) is the key element of the DCLL blanket concept. The FCI serves as electrical and thermal insulator to reduce the MHD pressure drop and to decouple the temperature-limited ferritic structure from the flowing hot lead-lithiu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6bb79a7193187c447b74541a8cf96e28
https://doi.org/10.1016/j.fusengdes.2016.04.035
https://doi.org/10.1016/j.fusengdes.2016.04.035
Publikováno v:
Journal of Nuclear Materials. 442:S302-S308
Surface micro-engineering can enhance the thermo-mechanical performance of plasma facing components (PFCs). For example, castellation of a surface can reduce thermal stress due to high heat loads and thus provide higher thermo-mechanical resilience.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::80e5917d05576e32e3359ce96b57d2f6
https://doi.org/10.1016/j.jnucmat.2013.05.004
https://doi.org/10.1016/j.jnucmat.2013.05.004
Publikováno v:
Journal of Nuclear Materials. 441:704-712
Structural steels for nuclear applications have undergone rapid development during the past few decades, thanks to a combination of trial-and-error, mechanism-based optimization, and multiscale modeling approaches. Deformation mechanisms are shown to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bcdb6fecf4de61137338199fb1392cf7
https://doi.org/10.1016/j.jnucmat.2013.03.045
https://doi.org/10.1016/j.jnucmat.2013.03.045
Publikováno v:
Fusion Science and Technology. 60:264-271
The U.S. Dual Coolant Lead Lithium (DCLL) ITER Test Blanket Module (TBM) is under development for operation in the ITER reactor. The DCLL TBM must satisfy the Structural Design Criteria for ITER In-vessel Components (SDC-IC), which provides rules for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3023f5134e7b3d768929ee5d80ebd751
https://doi.org/10.13182/fst11-a12363
https://doi.org/10.13182/fst11-a12363
Publikováno v:
Fusion Science and Technology. 60:208-212
A rectangular single channel low pressure drop helium-cooled refractory metal heat exchanger (HX) tube for divertor applications was designed and manufactured for testing in the SNL E-beam facility. A unique fabrication feature of the rectangular HX
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7aa884670360cbcb20c3cd9e72c4d01
https://doi.org/10.13182/fst11-a12353
https://doi.org/10.13182/fst11-a12353
Publikováno v:
Fusion Science and Technology. 60:203-207
A flat-plate He-cooled divertor would provide a flat surface facing the plasma, would minimize the number of otherwise complex sub-modules needed to cool large areas, and could greatly reduce the c...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8bbb7548c15f7a9dcdbf61c2feb846bf
https://doi.org/10.13182/fst10-293
https://doi.org/10.13182/fst10-293
Publikováno v:
Fusion Science and Technology. 60:170-174
The US Fusion Nuclear Science and Technology program selected the Dual Coolant Lead Lithium (DCLL) concept as the primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ace5adfbcb2d1a24416d0f9af8d0af98
https://doi.org/10.13182/fst11-a12347
https://doi.org/10.13182/fst11-a12347
Autor:
D.-K. Sze, Mohamed E. Sawan, K. Messadek, Mohamed A. Abdou, E. Marriott, Neil B. Morley, M.Z. Youssef, S. Willms, Richard J. Kurtz, Brad J. Merrill, Alice Ying, C.P.C. Wong, Siegfried Malang, Sergey Smolentsev, Yutai Katoh, M. Dagher, Shahram Sharafat
Publikováno v:
Fusion Engineering and Design. 85:1129-1132
Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEM
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27438a1e6df17c13b16b5a6f2c850a96
https://doi.org/10.1016/j.fusengdes.2010.02.021
https://doi.org/10.1016/j.fusengdes.2010.02.021
Publikováno v:
IEEE Transactions on Plasma Science. 38:2993-2998
As part of the U.S. ITER test blanket module development effort, several flow channel insert (FCI) concepts using a variety of porous SiC and SiC/SiC composites are being developed. Using porous SiC, prototypes of FCI segments as large as 0.12 m × 0
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5adf1c82853d768df448e083a50a4173
https://doi.org/10.1109/tps.2010.2058867
https://doi.org/10.1109/tps.2010.2058867