Results 81 to 90 of about 96,750 (196)

The effect of CD4 injection on WD molecule sputtering at the divertor target in EAST

Nuclear Materials and Energy
Tungsten (W) is one of the preferred plasma-facing materials for future fusion reactors because of the advantages of high melting point, low physical sputtering rate and low fuel retention.
Q. Zhang, F. Ding, B.C. Qi, L.Y. Meng, L. Yu, C.Y. Zhang, Z.H. Hu, R. Ding, L. Wang, H.S. Zhou, G.N. Luo, Z.S. Yang, X. Yang   +12 more
doaj   +1 more source

Batteries From Reused, Recycled, and Surplus Materials

Advanced Sustainable Systems, Volume 10, Issue 7, July 2026.
Batteries can become more circular by combining reuse, direct recycling, metallurgical recovery, and material sourcing from industrial surplus streams. This Review highlights how recycled and waste‐derived metals, carbons, polymers, electrolytes, and active materials can be reintegrated into current and emerging batteries, while emphasizing design ...
Jing Yu, Irina Martynova, Elsa Briqueleur, Michael Carboni, Pascale Chenevier, Giulia Pezzin, Yuchuan Ren, Malik Dilshad Khan, Zeyan Li, Marja Vilkman, Chamseddine Guizani, Mickael Dolle, Gian Andrea Blengini, Jordi Jacas, Jordi Arbiol, Andreu Cabot, Alessandra Manzini   +16 more
wiley   +1 more source

Overview of the KSTAR experiments and future plan

Nuclear Fusion
The Korea Superconducting Tokamak Advanced Research (KSTAR) device has recently entered a new phase of operation following the installation of a tungsten mono-block divertor, providing a unique platform to investigate high-performance, long-pulse plasma ...
Yong Un Nam, H. Han, H.H. Lee, J. Chung, Y.M. Jeon, G.Y. Park, J. Kim, K. Kim, M. Kim, J. Ko, S. Wang, Y.-C. Ghim, Y.S. Na, C. Sung, J.-K. Park, S.K. Kim, J.M. Park, S. Ding, H.Q. Wang, J. Lee, S.-H. Hahn, H.S. Kim, J.W. Juhn, K. Kim, J.H. Lee, J.H. Hwang, J.H. Kim, M.H. Woo, A.M. Garofalo, Q.M. Hu, D. Eldon, K. Kwon, S.A. Sabbagh, G. Bustos-Ramirez, J.D. Riquezes, M. Tobin, H.K. Lee, F.C. Sheehan, V. Zamkovska, J.R. Jepson, G.A. Tillinghast, J. Lee, S.M. Yang, A. Gupta, W.H. Ko, G. Shin, Y. Lee, J.K. Lee, B. Kim, S. Hong, Y.S. Park, J.G. Bak, M.J. Choi, E. Kim, M. Joung, S.J. Park, J.H. Jeong, S.G. Lee, B.H. Park, K. Erickson, J. Barr, C. Ham, A. Kirk, L. Kogan, J.H. Lee, K.D. Lee, D. Ryan, R. Shousha, A. Thornton, J. Yoo, B. Patel, D. Kim, S.H. Kim, H. Lee, J. Lee, W. Lee, E.N. Bang, H.-S. Kim, C.S. Byun, S.T. Oh, H. Schamis, E. Gilson, S.H Son, H.M. Wi, Y.S. Han, J.H. Yoon, D.C. Seo, J.H. Jang, S.H. Park, S. Kwon, S.W. Kwag, H.T. Kim, Y.B. Chang, N.H. Song, S. Hong, R.A. Pitts, A.A. Pshenov, H.Y. Jeong, M.K. Kim, K.P. Kim, C.R. Seon, J.I. Song, W. Jeong, Y.G. Lim, S.M. Bong, A. Nagy, V. Alarcon, F. Laggner, S.H. Park, H.M. Lee, A. Bortolon, R. Maingi, E. Kolemen, Y.O. Kim, I.S. Woo, C.Y. Lee, W. Cho, J.S. Kim, K. Lee, H. Kim, G.H. Park, J. Ko, J.-S. Lee, W.H. Choe, Y.S. Hwang, J.G. Kwak, W.C. Kim, S.W. Yoon, the KSTAR Team   +128 more
doaj   +1 more source

Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions

Nuclear Materials and Energy, 2017
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions in the T-10 tokamak. Significant melting, formation of small craters and erosion of the tungsten limiter have been observed after ∼400 discharges with ...
V.P. Budaev, Yu.V. Martynenko, S.A. Grashin, R.N. Giniyatulin, I.I. Arkhipov, A.V. Karpov, P.V. Savrukhin, E.A. Shestakov, R.Yu. Solomatin, L.B. Begrambekov, N.E. Belova, S.D. Fedorovich, L.N. Khimchenko, V.M. Safronov   +13 more
doaj   +1 more source

A new design concept of actively cooled plasma-facing units for the divertors of fusion reactors

Nuclear Materials and Energy
This paper sketches a new divertor design concept that solves most of the issues already identified with the actual ITER design, especially in what concerns transient heat loading. It resists ELM heat loads better than the present ITER design.
J.P. Gunn, M. Firdaouss, M. Richou, Claudio Maria De Simone   +3 more
doaj   +1 more source

Divertor detachment and heat exhaust mitigation control in KSTAR with tungsten divertor

Plasma Physics and Controlled Fusion
Abstract KSTAR has recently undergone an upgrade to use a new tungsten divertor to run experiments in ITER-relevant scenarios. Even with a high melting point of tungsten, it is important to control the heat flux impinging on tungsten divertor targets to minimize sputtering and contamination of the core plasma.
Anchal Gupta, David Eldon, Eunnam Bang, KyuBeen Kwon, Hyungho Lee, Anthony Leonard, Junghoo Hwang, Xueqiao Xu, Menglong Zhao, Ben Zhu   +9 more
openaire   +1 more source

Simulation study of tungsten erosion and impurity transport under the assumption of a full-tungsten wall in EAST plasmas

Nuclear Fusion
Future fusion reactors are expected to employ full-tungsten plasma-facing components (PFCs), and the generation and core accumulation of tungsten impurities under full-tungsten wall environment is one of the key issues that limit the stable operation of ...
Yihan Wu, Xuele Zhao, Chaofeng Sang, Yilin Wang, Chen Zhang, Qingrui Zhou, Dezhen Wang, Rui Ding, Baoguo Wang, Qingquan Yang, Yue Yu, Guoliang Xu, Fang Ding   +12 more
doaj   +1 more source

The impacts of lithium and silicon coating on the W source in EAST

Nuclear Materials and Energy, 2017
Application of lithium (Li) or silicon (Si) wall coating in the Experimental Advanced Superconducting Tokamak (EAST) has proven to be an effective method to reduce fuel recycling and control impurity level, and also to improve the plasma performance.
Hongmin Mao, Fang Ding, Guang-Nan Luo, Zhenhua Hu, Xiahua Chen, Feng Xu, Jiansheng Hu, Guizhong Zuo, Zhen Sun, Yaowei Yu, Jinhua Wu, Liang Wang, Yanmin Duan, Jichan Xu, Jingbo Chen, Zhongshi Yang, Rui Ding, Hai Xie   +17 more
doaj   +1 more source

EX/P4-16 Localized Tungsten Deposition in Divertor Region in JT-60U

, 2020
. Deposition profiles of tungsten released from the outer divertor were studied in JT-60U. A neutron activation method was used for the first time to accurately measure deposited tungsten.
Y Ueda
core  

Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET [PDF]

, 2013
Tungsten erosion in the outer divertor of the JET ITER like wall was quantified by spectroscopy. Effective sputtering yields of typically 10−4 were measured in L-mode at ∼30 eV attached divertor conditions and beryllium was identified as the main cause ...
G. J. van Rooij, Stamp, M. F., Dux, R., Neu, R., M. Groth, Puetterich, T, Clever, M, Matthews, G F, Brezinsek, S., Rooij, GJ Gerard van, S. Potzel, Coenen, J., Krieger, K, G.F. Matthews, A. Meigs, M.F. Stamp, Rapp, J., Matthews, G., S. Brezinsek, Dux, R, Aho-Mantila, Leena, van Rooij, G.J., Matthews, G. F., Coenen, J.W., L. Aho-Mantila, Stamp, M., Marsen, S, Stamp, M.F., Stamp, M F, Krieger, K., Meigs, A G, S. Marsen, van Rooij, G. J., Marsen, S., Rapp, J Jrgen, Potzel, S., Pütterich, T., Coenen, J. W., Matthews, G.F., Coenen, J W, Groth, M, Meigs, A., Potzel, S, K. Krieger, Clever, M., R. Dux, G.J. van Rooij, T. Pütterich, J.W. Coenen, M. Clever, Aho-Mantila, L, Brezinsek, S, Rooij, G., Aho-Mantila, L., Groth, M., J. Rapp, R. Neu, Neu, R   +57 more
core   +1 more source