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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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Thermo-mechanical analysis of the ICRH antenna for the ignitor experiment: Part I: Faraday shield

T. Berruti, M.M. Gola, M.F. Salvetti2005

Measurement of the depletion of neutraliser target due to gas heating in the JET neutral beam injection system

E. Surrey, C.D. Challis, D. Ciric, S.J. Cox, D. Keeling2005

EAST machine assembly and its measurement system

S.T. Wu, EAST Machine Team2005

Theoretical expressions for removing tritium from exhaust gas

Primary results of the upgraded actively cooled limiter system of HT-7

J.S. Hu, J.G. Li, X.D. Zhang, N.C. Luo, H. Li2005

Drucker–Prager–Cap creep modelling of pebble beds in fusion blankets

D. Hofer, M. Kamlah2005

Simulation on interactions of X-ray and charged particles with first wall for IFE reactor

Hiroyuki Furukawa, Yasuji Kozaki, Keiji Yamamoto, Tomoyuki Johzaki, Kunioki Mima2005

Code development for analysis of MHD pressure drop reduction in a liquid metal blanket using insulation technique based on a fully developed flow model

Sergey Smolentsev, Neil Morley, Mohamed Abdou2005

The ITER limiter support system with controlled position of the plasma facing modules

V. Rozov, A. Cardella, K. Ioki2005

Helium gas permeability of SiC/SiC composite used for in-vessel components of nuclear fusion reactor

T. Hino, E. Hayashishita, Y. Yamauchi, M. Hashiba, A. Kohyama2005

Design concepts for KSTAR plasma control system

Hogun Jhang, I.S. Choi2005

Effect of high doses of neutron irradiation on physico-mechanical properties of copper alloys for ITER applications

S.A. Fabritsiev, A.S. Pokrovsky2005

Evaluation of phase correcting mirrors for an 84 GHz gyrotron based on direct phase measurements at low-power level

T. Notake, H. Idei, T. Shimozuma, M. Sato, R.J. Temkin2005

Specimen size effects in the cryogenic fracture toughness testing of Fe–12Cr–12Ni–10Mn–0.24N stainless steel

Y. Shindo, K. Horiguchi, J. Yamada2005

Subject Index

Hazard evaluation of The International Fusion Materials Irradiation Facility

Luciano Burgazzi2004

Design of actively cooled flat toroidal limiter with CuCr heat sink for the HT-7 superconducting tokamak

Jiansheng Hu, Jiangang Li, Xiaodong Zhang, Nanchang Luo, Hua Li2004

Erosion, transport, and tritium codeposition analysis of a beryllium wall tokamak

Jeffrey N. Brooks, Jean Paul Allain, Darren A. Alman, David N. Ruzic2004

Optimization study on the normal conducting center post for the low aspect ratio tokamak reactor

Y. Song, S. Nishio2004

Retention and desorption of hydrogen and helium in stainless steel wall by glow discharge

T. Hino, Y. Yamauchi, S. Satoh, Y. Hirohata, O. Motojima2004

Heterogeneous breeding blanket experiment with lithium titanate and beryllium

A. Klix, Yu. Verzilov, K. Ochiai, T. Nishitani, A. Takahashi2004

Engineering and geometric aspects of the solid wall re-circulating fluid blanket based on advanced ferritic steel

I.N. Sviatoslavsky, M.E. Sawan, E.A. Mogahed, S. Majumdar, S. Sharafat2004

Safety assessment of two advanced ferritic steel molten salt blanket design concepts

B.J. Merrill, M. Sawan, C.P.C. Wong, R.E. Nygren, D.-K. Sze2004

Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel

C.P.C. Wong, S. Malang, M. Sawan, I. Sviatoslavsky, S. Sharafat2004

Design integration of liquid surface divertors

R.E. Nygren, D.F. Cowgill, M.A. Ulrickson, B.E. Nelson, M. Kotschenreuther2004

A fusion reactor design with a liquid first wall and divertor

R.E. Nygren, T.D. Rognlien, M.E. Rensink, S.S. Smolentsev, R. Majeski2004

Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

M. Kotschenreuther, T. Rognlien, P. Valanju2004

Ignited spherical tokamaks and plasma regimes with LiWalls

L.E. Zakharov, N.N. Gorelenkov, R.B. White, S.I. Krasheninnikov, G.V. Pereverzev2004

Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor

D.G. Whyte, T.E. Evans, C.P.C. Wong, W.P. West, J.N. Brooks2004

Testing of liquid lithium limiters in CDX-U

R. Majeski, R. Kaita, M. Boaz, P. Efthimion, V. Soukhanovskii2004

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