Zobrazeno 1 - 10
of 17 798
pro vyhledávání: '"Divertor"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2307-2316 (2024)
A melting failure of W monoblock components of the upper divertor outer target in EAST occurred during the plasma campaigns in 2019. The failure characters and microstructure evolution of the failed W monoblock have been well investigated on one stri
Externí odkaz:
https://doaj.org/article/051cf3fa8e6d416abd6e16e0164e9f4f
Autor:
Tao Huang, Qiuyue Nie, Tao Jiang, Cheng Chen, Yang Liu, Jinming Gao, Laizhong Cai, Xu Zhao, Xiaogang Wang
Publikováno v:
Frontiers in Physics, Vol 12 (2024)
As a high heat flux linear plasma device designed for studying divertor materials in future fusion reactors, HIT-PSI(Plasma Surface Interaction device at Harbin Institute of Technology) has been successfully constructed and has maintained stable oper
Externí odkaz:
https://doaj.org/article/a571b1279eb14bb9be10391dc1b2f34a
Autor:
Wu-Qingliang Peng, Yu-Ping Xu, Yu Tian, Huai-Zhi Li, Fang-Yong Du, Shou-An Puyang, Qiang Li, Hai-Shan Zhou, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101720- (2024)
Compared to CuCrZr, oxide dispersion strengthened copper alloy (ODS-Cu) exhibits higher stability of properties under irradiation and exposure to elevated temperatures, demonstrating broad application prospects in divertor components. Oxygen-free hig
Externí odkaz:
https://doaj.org/article/30b2e7f19ee34378944c8f3a39abf905
Autor:
Patrik Tarfila, Oriol Costa Garrido, Boštjan Končar, Emanuela Martelli, Francesco Giorgetti, Selanna Roccella
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101715- (2024)
A new Divertor Tokamak Test (DTT) facility is currently being built in Italy to investigate different divertor configurations under different plasma scenarios. The divertor and in particular its target, consisting of Plasma Facing Units (PFUs), is ex
Externí odkaz:
https://doaj.org/article/15c411e9766a4c1c917d9c8be65400f5
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101716- (2024)
The divertor must simultaneously withstand unprecedented high heat fluxes of up to 20 MW/m2 and high-energy neutron irradiation of 14-MeV during fusion reactor operation. Accordingly, it is necessary to simultaneously meet the excellent heat dissipat
Externí odkaz:
https://doaj.org/article/5d5d185e15cb43e88e64392e475069e5
Autor:
Armin Manhard
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101696- (2024)
Liquid metal divertors are discussed as a potential alternative to divertor components made entirely of solid materials such as tungsten. However, liquid metal interaction with H isotope plasmas poses entirely new challenges, including the stability
Externí odkaz:
https://doaj.org/article/26209fed05e04f60962561bdb98c51d0
Autor:
Haotian Yang, Ryo Yasuhara, Hiroyuki Noto, Daisuke Nagata, Masayuki Tokitani, Haruki Kawaguchi, Chihiro Suzuki, Reina Miyagawa, Hiyori Uehara
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101688- (2024)
The laser-induced grain structure of pure tungsten was evaluated using a nanosecond Q-switched Nd:YAG laser. The grain structure, crystal orientation, and grain boundary angular distribution were analyzed through electron backscatter diffraction anal
Externí odkaz:
https://doaj.org/article/55f2cbdae32a4d37b987c7d7b375520e
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:
Y. Anquetin, J. Gaspar, Y. Corre, JL. Gardarein, J. Gerardin, P. Malard, F. Rigollet, Q. Tichit, E. Tsitrone
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101788- (2024)
The estimation of the heat flux density distribution profiles in tokamak devices is a very important research topic for edge plasma physics purposes and also to ensure the safety of the machine. In the radial direction, the heat flux exhibits an expo
Externí odkaz:
https://doaj.org/article/e259c1d3e6494c1e8677d24880016b56
Autor:
S.S. Henderson, M. Bernert, D. Brida, G.L. Derks, S. Elmore, F. Federici, J.R. Harrison, A. Kirk, B. Kool, N. Lonigro, J. Lovell, D. Moulton, H. Reimerdes, P. Ryan, J.M. Stobbs, K. Verhaegh, T. van den Doel, T. Wijkamp, O. Bardsley
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101765- (2024)
Two reduced models for predicting detachment onset and divertor reattachment times are validated on MAST Upgrade (MAST-U). These models are essential for future tokamak reactor design, providing rapid calculations based primarily on engineering param
Externí odkaz:
https://doaj.org/article/e5bc0ceb8f1142bd8db882971ecc33b5