Digitale Bibliotheek
Sluiten Bladeren door artikelen uit een tijdschrift
     Tijdschrift beschrijving
       Alle jaargangen van het bijbehorende tijdschrift
         Alle afleveringen van het bijbehorende jaargang
                                       Alle artikelen van de bijbehorende aflevering
 
                             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
96-97 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
96-97 1-3 p. 169-177
9 p.
artikel
3 Current drive studies for the ARIES steady-state tokamak reactors Mau, T.K.
1994
96-97 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
96-97 1-3 p. 111-124
14 p.
artikel
5 Design integration of liquid surface divertors Nygren, R.E.
2004
96-97 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
96-97 1-3 p. 227-238
12 p.
artikel
7 Editor's introduction Najmabadi, Farrokh
1994
96-97 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
96-97 1-3 p. 307-326
20 p.
artikel
9 Evaluation of helium cooling for fusion divertors Baxi, C.B.
1994
96-97 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
96-97 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
96-97 1-3 p. 35-62
28 p.
artikel
12 Fusion-fission hybrid reactor research and development program in China Qiu, L.J.
1994
96-97 1-3 p. 105-109
5 p.
artikel
13 Fusion nuclear technology and materials: status and R&D needs Tillack, Mark
1994
96-97 1-3 p. 21-34
14 p.
artikel
14 Fusion reactor design and technology program in China Huang, J.H.
1994
96-97 1-3 p. 35-47
13 p.
artikel
15 Fusion reactor design and technology program in Japan Seki, Yasushi
1994
96-97 1-3 p. 49-66
18 p.
artikel
16 Fusion reactor design studies Seki, Yasushi
1994
96-97 1-3 p. 5-13
9 p.
artikel
17 HELIAS stellarator reactor studies and related European technology studies Grieger, G.
1994
96-97 1-3 p. 73-84
12 p.
artikel
18 Helium cooling of fusion reactors Wong, C.P.C.
1994
96-97 1-3 p. 249-262
14 p.
artikel
19 Ignited spherical tokamaks and plasma regimes with LiWalls Zakharov, L.E.
2004
96-97 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
96-97 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
96-97 1-3 p. 125-143
19 p.
artikel
22 Liquid metal integrated test system (LIMITS) Tanaka, T.J.
2004
96-97 1-3 p. 83-92
10 p.
artikel
23 Magnetohydrodynamic stability regimes for steady state and pulsed reactors Jardin, S.C.
1994
96-97 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
96-97 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
96-97 1-3 p. 145-157
13 p.
artikel
26 Plasma physics and plasma engineering: status and R&D needs Sokolov, Yu.A.
1994
96-97 1-3 p. 15-19
5 p.
artikel
27 Preface Abdou, Mohamed
2004
96-97 1-3 p. 1-2
2 p.
artikel
28 Progress on the European Safety and Environmental Assessment of Fusion Power (SEAFP) Cook, I.
1994
96-97 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
96-97 1-3 p. 3-34
32 p.
artikel
30 Safety analyses of the ARIES tokamak reactor designs Herring, J.Stephen
1994
96-97 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
96-97 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
96-97 1-3 p. 239-247
9 p.
artikel
33 Status of fusion reactor design and technology in Russia Sokolov, Yu.A.
1994
96-97 1-3 p. 67-72
6 p.
artikel
34 Status of the US stellarator reactor study Lyon, J.F.
1994
96-97 1-3 p. 85-103
19 p.
artikel
35 Strategic goals and development pathways for fusion Conn, R.W.
1994
96-97 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
96-97 1-3 p. 93-110
18 p.
artikel
37 Study of DEMO reactor concept in Russia Sokolov, Yu.A.
1994
96-97 1-3 p. 159-167
9 p.
artikel
38 Surface composition of liquid metals and alloys Bastasz, R.
2004
96-97 1-3 p. 111-119
9 p.
artikel
39 Testing of liquid lithium limiters in CDX-U Majeski, R.
2004
96-97 1-3 p. 121-132
12 p.
artikel
40 The concept of drastically easy maintenance (DREAM) tokamak reactor Nishio, S.
1994
96-97 1-3 p. 289-298
10 p.
artikel
41 Thermal and structural behaviour of various first-wall concepts Karditsas, Panayiotis J.
1994
96-97 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
96-97 1-3 p. 63-81
19 p.
artikel
                             42 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland