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                             42 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A fusion reactor design with a liquid first wall and divertor Nygren, R.E.
 2004
 1-3 p. 181-221
41 p.
 artikel
2 Conceptual design of a fusion-fission hybrid reactor for transmutation of high level nuclear waste Qiu, L.J.
 1994
 1-3 p. 169-177
9 p.
 artikel
3 Current drive studies for the ARIES steady-state tokamak reactors Mau, T.K.
 1994
 1-3 p. 205-214
10 p.
 artikel
4 Design descriptions of the Prometheus-L and -H inertial fusion energy drivers Linford, G.J.
 1994
 1-3 p. 111-124
14 p.
 artikel
5 Design integration of liquid surface divertors Nygren, R.E.
 2004
 1-3 p. 223-244
22 p.
 artikel
6 Design study of helium-solid suspension cooled blanket and divertor plate for a tokamak power reactor Yamazaki, Seiichiro
 1994
 1-3 p. 227-238
12 p.
 artikel
7 Editor's introduction Najmabadi, Farrokh
 1994
 1-3 p. ix-
1 p.
 artikel
8 Engineering and geometric aspects of the solid wall re-circulating fluid blanket based on advanced ferritic steel Sviatoslavsky, I.N.
 2004
 1-3 p. 307-326
20 p.
 artikel
9 Evaluation of helium cooling for fusion divertors Baxi, C.B.
 1994
 1-3 p. 263-271
9 p.
 artikel
10 Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor Whyte, D.G.
 2004
 1-3 p. 133-147
15 p.
 artikel
11 Exploratory studies of flowing liquid metal divertor options for fusion-relevant magnetic fields in the MTOR facility Ying, A.Y.
 2004
 1-3 p. 35-62
28 p.
 artikel
12 Fusion-fission hybrid reactor research and development program in China Qiu, L.J.
 1994
 1-3 p. 105-109
5 p.
 artikel
13 Fusion nuclear technology and materials: status and R&D needs Tillack, Mark
 1994
 1-3 p. 21-34
14 p.
 artikel
14 Fusion reactor design and technology program in China Huang, J.H.
 1994
 1-3 p. 35-47
13 p.
 artikel
15 Fusion reactor design and technology program in Japan Seki, Yasushi
 1994
 1-3 p. 49-66
18 p.
 artikel
16 Fusion reactor design studies Seki, Yasushi
 1994
 1-3 p. 5-13
9 p.
 artikel
17 HELIAS stellarator reactor studies and related European technology studies Grieger, G.
 1994
 1-3 p. 73-84
12 p.
 artikel
18 Helium cooling of fusion reactors Wong, C.P.C.
 1994
 1-3 p. 249-262
14 p.
 artikel
19 Ignited spherical tokamaks and plasma regimes with LiWalls Zakharov, L.E.
 2004
 1-3 p. 149-168
20 p.
 artikel
20 Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls Kotschenreuther, M.
 2004
 1-3 p. 169-180
12 p.
 artikel
21 Innovation leads the way to attractive inertial fusion energy reactors–Prometheus-L and Prometheus-H Waganer, Lester M.
 1994
 1-3 p. 125-143
19 p.
 artikel
22 Liquid metal integrated test system (LIMITS) Tanaka, T.J.
 2004
 1-3 p. 83-92
10 p.
 artikel
23 Magnetohydrodynamic stability regimes for steady state and pulsed reactors Jardin, S.C.
 1994
 1-3 p. 215-225
11 p.
 artikel
24 Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel Wong, C.P.C.
 2004
 1-3 p. 245-275
31 p.
 artikel
25 Osiris and SOMBRERO inertial fusion power plant designs–summary, conclusions, and recommendations Meier, Wayne R.
 1994
 1-3 p. 145-157
13 p.
 artikel
26 Plasma physics and plasma engineering: status and R&D needs Sokolov, Yu.A.
 1994
 1-3 p. 15-19
5 p.
 artikel
27 Preface Abdou, Mohamed
 2004
 1-3 p. 1-2
2 p.
 artikel
28 Progress on the European Safety and Environmental Assessment of Fusion Power (SEAFP) Cook, I.
 1994
 1-3 p. 179-191
13 p.
 artikel
29 Progress on the modeling of liquid metal, free surface, MHD flows for fusion liquid walls Morley, N.B.
 2004
 1-3 p. 3-34
32 p.
 artikel
30 Safety analyses of the ARIES tokamak reactor designs Herring, J.Stephen
 1994
 1-3 p. 193-204
12 p.
 artikel
31 Safety assessment of two advanced ferritic steel molten salt blanket design concepts Merrill, B.J.
 2004
 1-3 p. 277-306
30 p.
 artikel
32 Some aspects of gas-solid suspension flows in relation to cooling of the divertor and blanket Shimizu, Akihiko
 1994
 1-3 p. 239-247
9 p.
 artikel
33 Status of fusion reactor design and technology in Russia Sokolov, Yu.A.
 1994
 1-3 p. 67-72
6 p.
 artikel
34 Status of the US stellarator reactor study Lyon, J.F.
 1994
 1-3 p. 85-103
19 p.
 artikel
35 Strategic goals and development pathways for fusion Conn, R.W.
 1994
 1-3 p. 1-4
4 p.
 artikel
36 Studies of liquid-metal erosion and free surface flowing liquid lithium retention of helium at the University of Illinois Allain, J.P.
 2004
 1-3 p. 93-110
18 p.
 artikel
37 Study of DEMO reactor concept in Russia Sokolov, Yu.A.
 1994
 1-3 p. 159-167
9 p.
 artikel
38 Surface composition of liquid metals and alloys Bastasz, R.
 2004
 1-3 p. 111-119
9 p.
 artikel
39 Testing of liquid lithium limiters in CDX-U Majeski, R.
 2004
 1-3 p. 121-132
12 p.
 artikel
40 The concept of drastically easy maintenance (DREAM) tokamak reactor Nishio, S.
 1994
 1-3 p. 289-298
10 p.
 artikel
41 Thermal and structural behaviour of various first-wall concepts Karditsas, Panayiotis J.
 1994
 1-3 p. 273-287
15 p.
 artikel
42 Thermofluid modeling and experiments for free surface flows of low-conductivity fluid in fusion systems Smolentsev, S.
 2004
 1-3 p. 63-81
19 p.
 artikel
                             42 gevonden resultaten
 
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