nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A comparison of pulsed and steady-state tokamak reactor burn cycles. Part II: Magnet fatigue, power supplies, and cost analysis
|
Ehst, D.A. |
|
1985 |
|
3 |
p. 319-336 18 p. |
artikel |
2 |
A comparison of pulsed and steady-state tokamak reactor burn cycles. Part I: Thermal effects and lifetime limitations
|
Ehst, D.A. |
|
1985 |
|
3 |
p. 305-318 14 p. |
artikel |
3 |
A cross-section sensitivity and uncertainty analysis of fusion reactor blankets with SAD/SED effect
|
Furuta, Kazuo |
|
1986 |
|
3 |
p. 287-300 14 p. |
artikel |
4 |
3. Advanced design of the R-Tokamak
|
Matsuoka, K. |
|
1987 |
|
3 |
p. 335-355 21 p. |
artikel |
5 |
4. Alpha-particle diagnostics in the reacting plasma experiment
|
Sato, K.N. |
|
1987 |
|
3 |
p. 399-403 5 p. |
artikel |
6 |
An aluminum vacuum vessel for a low radioactivity fusion device in near future D-T experiment
|
Ioki, K. |
|
1984 |
|
3 |
p. 287-300 14 p. |
artikel |
7 |
An analysis of stress and strain for orthotropic toroidal shells
|
Xia, Zhixi |
|
1986 |
|
3 |
p. 309-318 10 p. |
artikel |
8 |
Announcement
|
|
|
1986 |
|
3 |
p. 319- 1 p. |
artikel |
9 |
A numerical model for swirl flow cooling in high-heat-flux particle beam targets and the design of a swirl-flow-based plasma limiter
|
Milora, S.L. |
|
1986 |
|
3 |
p. 301-308 8 p. |
artikel |
10 |
Author index to volume 2
|
|
|
1985 |
|
3 |
p. 417-418 2 p. |
artikel |
11 |
Author index to volume 4
|
|
|
1987 |
|
3 |
p. 447-448 2 p. |
artikel |
12 |
Comparison of lifetime calculation for fusion reactor first walls based on two creep-fatigue design criteria
|
Adegbulugbe, A.O. |
|
1984 |
|
3 |
p. 301-305 5 p. |
artikel |
13 |
Contents of part I
|
|
|
1987 |
|
3 |
p. 271- 1 p. |
artikel |
14 |
Contents of part II
|
|
|
1987 |
|
3 |
p. 359- 1 p. |
artikel |
15 |
Contents of part III
|
|
|
1987 |
|
3 |
p. 423- 1 p. |
artikel |
16 |
Control of plasma vertical position in tokamak reactors
|
Kameari, Akihisa |
|
1985 |
|
3 |
p. 365-373 9 p. |
artikel |
17 |
Design and safety study of power producing fusion-fission hybrid reactor
|
Furuta, Kazuo |
|
1984 |
|
3 |
p. 255-263 9 p. |
artikel |
18 |
Design, fabrication and performance test of JT-60 — Structural and thermal aspects
|
Shimizu, M. |
|
1986 |
|
3 |
p. 249-264 16 p. |
artikel |
19 |
3. Development of a high power ion source and a neutral beam injector on a 10 MW test stand
|
Oka, Y. |
|
1987 |
|
3 |
p. 387-397 11 p. |
artikel |
20 |
2.1. Development of low activation Al alloys for the R-project
|
Kamada, Kohji |
|
1987 |
|
3 |
p. 363-373 11 p. |
artikel |
21 |
1. Introduction
|
Miyahara, A. |
|
1987 |
|
3 |
p. 361-362 2 p. |
artikel |
22 |
1. Introduction
|
Hamada, Y. |
|
1987 |
|
3 |
p. 273-274 2 p. |
artikel |
23 |
Limiter damage due to over-heat load in doublet III tokamak
|
Yokomizo, H. |
|
1984 |
|
3 |
p. 279-285 7 p. |
artikel |
24 |
2. Low activation design of the R-tokamak
|
Hamada, Y. |
|
1987 |
|
3 |
p. 275-333 59 p. |
artikel |
25 |
Mechanical design assessments of structural components and auxiliaries of the Joint European Torus
|
Sonnerup, L. |
|
1986 |
|
3 |
p. 233-247 15 p. |
artikel |
26 |
Miniature tensile test specimens for fusion reactor irradiation studies
|
Klueh, R.L. |
|
1985 |
|
3 |
p. 407-416 10 p. |
artikel |
27 |
Optimization of OH coil recharging scenario of quasi-steady operation in tokamak fusion reactor by lower hybrid wave current drive
|
Sugihara, Masayoshi |
|
1984 |
|
3 |
p. 265-277 13 p. |
artikel |
28 |
Part I. Conceptual design of the R-tokamak
|
Hamada, Y. |
|
1987 |
|
3 |
p. v- 1 p. |
artikel |
29 |
Part III. Preliminary surveillance of prospective site — environmental considerations —
|
Obayashi, H. |
|
1987 |
|
3 |
p. 421- 1 p. |
artikel |
30 |
Part II. R & D efforts for the R-tokamak components
|
Miyahara, A. |
|
1987 |
|
3 |
p. 357- 1 p. |
artikel |
31 |
Preface
|
Miyahara, Akira |
|
1987 |
|
3 |
p. i-ii nvt p. |
artikel |
32 |
Preliminary surveillance of prospective site — environmental considerations —
|
Obayashi, H. |
|
1987 |
|
3 |
p. 425-446 22 p. |
artikel |
33 |
Protective interior wall for the doublet III vacuum vessel
|
Phelps, R.D. |
|
1985 |
|
3 |
p. 375-381 7 p. |
artikel |
34 |
Radiation hazards due to activated corrosion and neutron sputtering products in fusion reactor coolant and tritium breeding fluids
|
Klein, A.C. |
|
1985 |
|
3 |
p. 355-363 9 p. |
artikel |
35 |
Radiation shielding considerations for the repair and maintenance of a swimming pool-type tokamak reactor
|
Seki, Yasushi |
|
1984 |
|
3 |
p. 243-253 11 p. |
artikel |
36 |
6. Research and development on the tritium handling technology in the R-project
|
Amano, H. |
|
1987 |
|
3 |
p. 411-420 10 p. |
artikel |
37 |
2.2. Studies on hydrogen behaviour in surface layers of candidate materials for the R-project
|
Yamaguchi, S. |
|
1987 |
|
3 |
p. 375-385 11 p. |
artikel |
38 |
Subject index to volume 4
|
|
|
1987 |
|
3 |
p. 449-450 2 p. |
artikel |
39 |
Subject index to volume 2
|
|
|
1985 |
|
3 |
p. 419-420 2 p. |
artikel |
40 |
Surface melting and evaporation during disruptions in magnetic fusion reactors
|
Hassanein, A.M. |
|
1984 |
|
3 |
p. 307-324 18 p. |
artikel |
41 |
The ASDEX Upgrade toroidal field magnet and poloidal divertor field coil system adapted to reactor requirements
|
Köppendörfer, W. |
|
1986 |
|
3 |
p. 265-272 8 p. |
artikel |
42 |
The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications
|
Klueh, R.L. |
|
1985 |
|
3 |
p. 383-389 7 p. |
artikel |
43 |
The fracture of austenitic and martensitic steel in liquid lithium
|
Borgstedt, H.U. |
|
1986 |
|
3 |
p. 273-286 14 p. |
artikel |
44 |
The stopping of deuterons in lithium
|
Dierckx, R. |
|
1985 |
|
3 |
p. 337-354 18 p. |
artikel |
45 |
Time independent tensile behaviour of a high manganese steel selected as a candidate material in conceptual tokamak fusion reactor designs
|
Piatti, G. |
|
1985 |
|
3 |
p. 391-406 16 p. |
artikel |
46 |
5. Vacuum system
|
Uritani, A. |
|
1987 |
|
3 |
p. 405-409 5 p. |
artikel |