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Fusion Engineering and Design

Fusion Engineering and Design

An International Journal for Fusion Energy and Technology devoted to Experiments, Theory, Methods and Design

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1.7

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3.7

最新論文

Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation

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Tritium inventory issues for future reactors: choices, parameters, limits

D.K. Murdoch, Ch. Day, P. Gierszewski, R.-D. Penzhorn, C.H. Wu1999

Safety and environment aspects of a fusion power reactor

G Marbach, I Cook1999

The ultimate safety margins of ITER: a demonstration of the safety potential of fusion

David A Petti, Hans-Werner Bartels1999

Comparative thermal cyclic test of different beryllium grades previously subjected to simulated disruption loads

A Gervash, R Giniyatulin, I Mazul1999

European development of the ITER divertor target

G Vieider, M Merola, J.P Bonal, P Chappuis, C.H Wu1999

ITER divertor, design issues and research and development

R. Tivey, T. Ando, A. Antipenkov, V. Barabash, G. Vieider1999

Limitations on blanket performance

Objectives feasibility assessment of the water-cooled lithium–lead mock-up testing in ITER

L Giancarli, G Benamati, B Bielak, M.A Fütterer, J Szczepanski1999

ITER reference breeding blanket design

M Ferrari, A Bianchi, G Celentano, W Dänner, F Zacchia1999

Engineering design of the ITER blanket and relevant research and development results

F Elio, K Ioki, P Barabaschi, L Bruno, H Takatsu1999

The ITER toroidal field model coil (TFMC)

E Salpietro, R Maix, G Bevilacqua, G Di Bartolo, G.E Tardivelli1999

ITER magnet design and R&D

ITER achievements by July 1998 and future prospects

Structural design and manufacturing of TPE-RX vacuum vessel

H Sago, J Orita, H Kaguchi, Y Ishigami, H Koguchi1999

Benchmarking of evaluated nuclear data for bismuth by spherical shell transmission experiments with central T(d,n) and Cf-252 neutron sources

S.P Simakov, B.V Devkin, M.G Kobozev, V.A Talalaev, U von Möllendorff1999

Continuous monitoring of lithium in dynamic Pb–17Li systems

Multipoint vessel-temperature monitoring system for TPE-RX

Y Yagi, H Sakakita, H Koguchi, S Sekine1999

Extensive magnetic measurement system for TPE-RX

Y. Yagi, H. Sakakita, S. Sekine, H. Koguchi, T. Osakabe1999

Characterizing the uniformity of polystyrene and TPX z-pinch fusion targets by nuclear microscopy

A.J Antolak, D.H Morse, D.E Hebron, R.J Leeper, D Schroen-Carey1999

Development of popup Langmuir probe system for the JET MkIIa divertor

S.J Davies, X Tellier, G.F Matthews, C.H Wilson1999

Leak detection system in ITER

S Hiroki, P Ladd, K Shaubel, G Janeschitz, R.A Marrs1999

Monte Carlo analysis of helium production in the ITER shielding blanket module

Satoshi Sato, Hiromasa Iida, Romano Plenteda, Robert T Santoro1999

Numerical study for design of the passive stabilizer and its impact on MHD stability in the proposed KSTAR plasma

D.-Y. Lee, C.S. Chang, J. Manickam, N. Pomphrey, S.C. Jardin1999

Development of a power electrode for plasma biasing on RFX

D Desideri, A De Lorenzi, P Zaccaria1999

Results from Monte Carlo simulations of the neutron transport for the new 2.45 MeV neutron time-of-flight spectrometer for the JT-60U tokamak

M Hoek, T Nishitani, H Takahashi, M Nakazawa, T Elevant1999

Front-end system of the TPE-RX reversed-field pinch machine

Y. Yagi, S. Sekine, T. Shimada, A. Masiello, Y. Ishigami1999

Design concept and confinement prediction of TPE-RX reversed-field pinch device

Y. Yagi, S. Sekine, H. Sakakita, H. Koguchi, K. Sugisaki1999

Critical heat flux analysis and R&D for the design of the ITER divertor

A.R. Raffray, J. Schlosser, M. Akiba, M. Araki, D. Youchison1999

Test of the EURATOM LCT coil (NbTi conductor) with forced flow He II cooling

M Darweschsad, S Fink, G Friesinger, A Grünhagen, G Zahn1999

Thick boron carbide coatings for protection of tokamak first wall and divertor

O.I. Buzhinskij, Yu.M. Semenets1999

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