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 |