Zobrazeno 1 - 10
of 31
pro vyhledávání: '"W.T Reiersen"'
Autor:
G.S Lee, J Kim, S.M Hwang, C.S Chang, H.Y Chang, M.H Cho, B.H Choi, K Kim, K.W Cho, S Cho, K.K Choh, C.H Choi, J.H Choi, J.W Choi, I.S Choi, C.J Do, T.H Ha, J.H Han, J.S Hong, K.H Hong, N.I Hur, I.S Hwang, K.H Im, H.G Jhang, Y.S Jung, B.C Kim, D.L Kim, G.H Kim, H.S Kim, J.S Kim, J.Y Kim, W.C Kim, Y.S Kim, K.H Kwon, M.C Kyum, B.J Lee, D.K Lee, H.G Lee, J.M Lee, S.G Lee, H.G Na, Y.K Oh, J.H Park, H.C Ri, Y.S Ryoo, K.Y Song, H.L Yang, J.G Yang, B.J Yoo, S.J Yoo, N.S Yoon, S.B Yoon, G.H You, K.I You, W Choe, D.-I Choi, S.G Jeong, D.Y Lee, Y.S Bae, H.S Kang, G.N Kim, I.S Ko, W Namkung, J.S Oh, Y.D Bae, Y.S Cho, B.G Hong, G Hong, C.K Hwang, S.R In, M.H Ju, H.J Lee, B.H Oh, B.J Yoon, S Baang, H.J Choi, J Hwang, M.G Kim, Y.J Kim, S.I Lee, J Yee, C.S Yoon, K.-H Chung, S.H Hong, Y.S Hwang, S.H Kim, Y.H Kim, K.H Chung, J.Y Lim, D.W Ha, S.S Oh, K.S Ryu, Q.L Wang, T.K Ko, J Joo, S Suh, J.H Lee, Y.W Lee, H.S Shin, I.H Song, J Baek, I.Y Han, Y Koh, P.Y Park, C Ryu, J.J Cho, D.M Hwang, J.A Schmidt, H.K Park, G.H Neilson, W.T Reiersen, R.T Simmons, S Bernabei, F Dahlgren, L.R Grisham, S.C Jardin, C.E Kessel, J Manickam, S.S Medley, N Pomphrey, J.C Sinnis, T.G Brown, R.B White, K.M Young, J Schultz, P.W Wang, L Sevier, M.D Carter, P.M Ryan, D.W Swain, D.N Hill, W.M Nevins, B.J Braams
Publikováno v:
Nuclear Fusion. 40:575-582
The Korea Superconducting Tokamak Advanced Research (KSTAR) project is the major effort of the national fusion programme of the Republic of Korea. Its aim is to develop a steady state capable advanced superconducting tokamak to establish a scientific
Autor:
G.H. Neilson, W.T. Reiersen
Publikováno v:
21st IEEE/NPS Symposium on Fusion Engineering SOFE 05.
The National Compact Stellarator Experiment (NCSX) is under construction at Princeton Plasma Physics Laboratory (PPPL). The stellarator is a complex, 3-D assembly that has been designed by a team of engineers from the partner institutions, Oak Ridge
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
The Compact Ignition Tokamak (CIT) is planned as the next major step in the US fusion program. Its overall objective is to produce ignited plasma discharges. In order to realize this objective, plasma parameters which are consistent with recognized t
Autor:
W.T. Reiersen
Publikováno v:
15th IEEE/NPSS Symposium. Fusion Engineering.
The Tokamak Physics Experiment (TPX) is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. TPX has a long pulse (1000s) capability, can accommodate high divertor heat loads, has a flexible PF sys
Autor:
null G.H. Neilson, null M.C. Zarnstorff, null L.P. Ku, null E.A. Lazarus, null P.K. Mioduszewski, null M. Fenstermacher, null E. Fredrickson, null G.Y. Fu, null A. Grossman, null P.J. Heitzenroeder, null R.H. Hatcher, null S.P. Hirshman, null S.R. Hudson, null D.W. Johnson, null H.W. Kugel, null J.F. Lyon, null R. Majeski, null D.R. Mikkelsen, null D.A. Monticello, null B.E. Nelson, null N. Pomphrey, null W.T. Reiersen, null A.H. Reiman, null P.H. Rutherford, null J.A. Schmidt, null D.A. Spong, null D.J. Strickler
Compact stellarators have the potential to make steady-state, disruption-free magnetic fusion systems with beta approximately 5% and relatively low aspect ratio (R/ < 4.5) compared to most drift-optimized stellarators. Magnetic quasi-symmetry can be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ac5dac8c13b72786f6583ffffe8c2368
https://doi.org/10.2172/809845
https://doi.org/10.2172/809845
Autor:
W.T. Reiersen
The Tokamak Physics Experiment (TPX) is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. TPX has a long pulse (1000s) capability, can accommodate high divertor heat loads, has a flexible poloid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::145279b8a8036a589654d9da0f3e5df5
https://doi.org/10.1016/b978-0-444-82220-8.50170-9
https://doi.org/10.1016/b978-0-444-82220-8.50170-9
Autor:
W.T. Reiersen, G.H. Neilson
Publikováno v:
21st IEEE/NPS Symposium on Fusion Engineering SOFE 05; 2005, p1-4, 4p
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