Zobrazeno 1 - 10
of 14 323
pro vyhledávání: '"Iter"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 2990-2998 (2024)
In ITER, the evaluation of the activated water radiation source and its impact on the radiological levels is necessary to demonstrate compliance with the safety requirements. The use of simplified or conservative approaches often results in the appli
Externí odkaz:
https://doaj.org/article/bad2976e51574e17829fcf6d81fcc11d
Autor:
Hooton, Brian, author
Publikováno v:
Understanding Nuclear Reactors : Global Warming and the Hydrogen Strategy, 2024, ill.
Externí odkaz:
https://doi.org/10.1093/oso/9780198902652.003.0012
Autor:
J.A. Snipes, L.R. Baylor, A. Bortolon, F. Effenberg, E.P. Gilson, A. Loarte, R. Lunsford, R. Maingi, S. Meitner, F. Nespoli, S. Maruyama, A. Nagy, Z. Sun, J. Ulreich, T. Wauters
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101809- (2024)
As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to sup
Externí odkaz:
https://doaj.org/article/94ef5a3158bf4a17a41b69744de7ab2a
Autor:
Federico Pesamosca, Timo Ravensbergen, Richard A. Pitts, Domenico Frattolillo, Mattia Erroi, Quentin Deliege, Peter C. de Vries, Luca Zabeo, Luigi Pangione, Ivo S. Carvalho, Anna Vu
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101781- (2024)
Real-time monitoring and control of thermal loads on tungsten plasma-facing components is mandatory for ITER to avoid their overheating during plasma discharges. For the Start of Research Operations (SRO) phase, dedicated First Wall Heat Load Control
Externí odkaz:
https://doaj.org/article/325f068298784394be89736f8a7f30d2
Autor:
J. Gerardin, Y. Corre, C. Desgranges, M. Diez, L. Dubus, M. Firdaouss, J. Gaspar, A. Grosjean, C. Guillemaut, C. Hernandez, A. Huart, H. Roche, S. Vives
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101783- (2024)
After 3 h of accumulated time from repeated plasma shots during C7 campaign performed in 2023, a deposited layer appeared on the ITER-grade W-monoblock of the lower divertor of WEST, mostly on the high field side. The growth of the deposit was observ
Externí odkaz:
https://doaj.org/article/1a182519497840239fbbaf4daade2212
Autor:
S. Sureshkumar, N. Rivals, P. Tamain, X. Bonnin, R. Pitts, Y. Marandet, G. Ciraolo, H. Bufferand, G. Falchetto, N. Fedorczak, V. Quadri, M. Raghunathan, F. Schwander, E. Serre, R. Düll, N. Varadarajan
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101780- (2024)
Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation. A key missing feature of existing SOLPS simulations (Pitts et al., 2019) is the absence of a
Externí odkaz:
https://doaj.org/article/00c27ea3e4cf412fbbac8815ac604176
Autor:
M. Scotto d’Abusco, I. Kudashev, G. Giorgiani, A. Glasser-Medvedeva, F. Schwander, E. Serre, J. Bucalossi, H. Bufferand, G. Ciraolo, P. Tamain
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101750- (2024)
This work explores the Limiter–Divertor transition (L–D) during the current ramp-up of ITER’s Q = 10 baseline plasma scenario at various central line-integrated density nli values. The analysis, based on transport simulations performed with the
Externí odkaz:
https://doaj.org/article/9284628542dd46b9ab57a3ac23c4b0c3
Autor:
E.D. Emdee, R.J. Goldston
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101737- (2024)
Recent calculations of the lithium vapor box divertor using SOLPS have demonstrated that far Scrape-Off Layer (SOL) baffling and the corresponding far SOL lithium evaporation are unnecessary for divertor performance. The plasma, acting as a virtual b
Externí odkaz:
https://doaj.org/article/01a1b6eb50c24d2c8f5fbeab0e006497
Autor:
Yang Wang, Dahuan Zhu, Chuannan Xuan, Zongxiao Guo, Chunyu He, Binfu Gao, Baoguo Wang, Rui Ding, Junling Chen
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101665- (2024)
W/Cu monoblocks will be employed in ITER as divertor targets for high heat loads. Experimental results of W/Cu monoblocks in high heat flux (HHF) tests have demonstrated their endurance on 5000 cycles at 10 MW/m2 and occasionally 300 cycles at 20 MW/
Externí odkaz:
https://doaj.org/article/64c1109e0aa74231a4e85d4207c47d3c