Fusion Engineering and Design

Items from 1 to 20 out of 9,681 results

article

The tubular separate first wall for ITER-EDA

A. Pizzuto, B. Riccardi, E. Salpietro, G. Malavasi

Fusion Engineering and Design > 1995 > 27 > 382-387

The first wall (FW) is one of the most loaded plasma-facing components; the heat flux is such that the thermal stresses are the most important design concern. In addition, the FW must resist the eddy current induced during plasma disruption and the high pressure of the coolant and should maintain its properties under a fast neutron flux (dose up to 3 MW m ^- ² ).The tubular solution is...

article

Analysis of the tokamak volumetric neutron source (VNS) design and range of its parameters

A.B. Mineev

Fusion Engineering and Design > 1995 > 27 > 307-315

article

Impact of JET experimental results and engineering development on the definition of the ITER design concept

JET Team, Enzo Bertolini

Fusion Engineering and Design > 1995 > 27 > 27-38

The concept and the key features of the Joint European Torus (JET), flagship of the integrated European fusion research programme, departed considerably from those of other large tokamaks under design in the early 1970s. D-shape toroidal coils and vacuum vessel and large volume high current plasma were unique and controversial features of JET. Moreover, since the early phase of the JET design, due...

article

MHD flow in rectangular ducts with inclined non-uniform transverse magnetic field

Thanh Q. Hua, John S. Walker

Fusion Engineering and Design > 1995 > 27 > 703-710

This paper examines the three-dimensional liquid metal MHD flow in rectangular ducts with thin conducting walls and with an inclined non-uniform transverse magnetic field. The Hartmann number and interaction parameter are assumed to be large and the magnetic Reynolds number is assumed to be small. Under these assumptions, viscous and inertial effects are confined to thin boundary layers adjacent...

article

Development of a direct insulation layer for a self-cooled liquid metal fusion reactor blanket

H.U. Borgstedt, H. Glasbrenner

Fusion Engineering and Design > 1995 > 27 > 659-662

The magneto-hydrodynamic (MHD) pressure drop in a self-cooled liquid metal fusion reactor blanket can be significantly reduced by means of electrical insulation of the flowing liquid metal against the structural material. Since alumina is chemically stable against Pb--17Li at up to 500 °C, direct insulation of MANET steel was performed by aluminizing the steel, using a hot-dip process followed by...

article

Dynamic behavior of fusion structural components under strong magnetic fields

T. Takagi, J. Tani, Y. Matsubara, I. Mogi

Fusion Engineering and Design > 1995 > 27 > 481-489

This paper describes dynamic behavior of non-ferromagnetic and ferromagnetic plates, and a non-ferromagnetic cylinder under strong magnetic field. The dynamic behavior of a ferromagnetic cantilevered plate, which is set along the uniform magnetic field, shows that its natural frequency increases with external magnetic induction. This means that a magnetic stiffness effect occurs in a ferromagnetic...

article

Impact of the passive stabilization system on the dynamic loads of the ITER first wall/blanket during a plasma disruption event

M. Ferrari, L. Anzidei, V. Cristini, G. Simbolotti

Fusion Engineering and Design > 1995 > 27 > 507-514

In next-generation tokamak devices (i.e. ITER), passive stabilization of the plasma is required to mitigate the consequences of the plasma vertical displacements and to reduce the occurrence of plasma disruptions. With this aim, two main design approaches have been considered. The first one (adopted in the ITER CDA design) consists of copper stabilization loops (twin loops) attached to box-shaped...

article

Disruption problematics in segmented-blanket concepts

Y.R. Crutzen, S. Fantechi, F. Farfaletti-Casali, A. Inzaghi, more

Fusion Engineering and Design > 1995 > 27 > 372-381

In tokamaks, the hostile operating environment originated by plasma disruption events requires that the first-wall/blanket/shield components sustain the large induced electromagnetic (EM) forces without significant structural deformation and within allowable material stresses. As a consequence, there is a need to improve the safety features of the segmented-blanket design concepts in order to satisfy...

article

Cracking susceptibility of stainless steel subjected to plasma disruption

Haruki Madarame, Toshio Sukegawa, Hiroshige Inoue

Fusion Engineering and Design > 1995 > 27 > 499-506

The similarities and differences in the cracking susceptibility between welding and resolidification after plasma disruption were examined experimentally using a number of primary candidate alloy samples with different chemical compositions. The product of the number density and the average depth of the cracks was measured after simulated disruption, employing a hydrogen ion beam as the heat source,...

article

Transient thermal and dynamic stresses in strongback-design blankets

Saurin Majumdar

Fusion Engineering and Design > 1995 > 27 > 430-437

Transient thermal stresses are compared for strongback-design blankets that contain stainless steel, ferritic steel, or a vanadium alloy as structural material. Transient dynamic stresses due to plasma disruptions are computed on a parametric basis. Disruption loading characteristics, for which transient effects are important, are identified. Also explored are the relative merits of supporting...

article

Helium induced swelling and tritium trapping mechanisms in irradiated beryllium: a comprehensive approach

F. Scaffidi-Argentina, M. Dalle Donne, C. Ferrero, C. Ronchi

Fusion Engineering and Design > 1995 > 27 > 275-282

Since beryllium is considered one of the best neutron multipliers for the blanket of a fusion reactor, several studies have been initiated to evaluate its behaviour under irradiation for both typical operating and accidental conditions. In the present work the effects of neutron irradiation on the mechanical properties of beryllium were studied with the aid of a computer code describing the most...

article

Reduction of toroidal ripple by using high T _c superconductors

Tetsuya Uchimoto, Kenzo Miya, Yoshikatsu Yoshida

Fusion Engineering and Design > 1995 > 27 > 528-535

In this paper we present a new method to reduce the toroidal ripple with use of high T _c superconductors. High <T _c superconductors can behave as ferromagnetic or diamagnetic materials depending on their magnetic hysteresis. If they are appropriately arranged and magnetized between the toroidal field coils, they possibly decrease the toroidal field ripple. Here, the preliminary...

article

A European proposal for an ITER water-cooled solid breeder blanket

P. Lorenzetto, P. Gierszewski, G. Simbolotti

Fusion Engineering and Design > 1995 > 27 > 423-429

The water-cooled solid breeder blanket concept proposed here aims to replace the shielding blanket for the enhanced performance phase of the international thermonuclear experimental reactor (ITER). The nominal performances are as follows: an average neutron wall load of 1 MW m ^- ² which corresponds to a fusion power of about 1.5 GW, and an average neutron fluence of 1 MWy m ^- ...

article

Thermomechanical interaction of particle bed-structural wall in a layered configuration Part II: Combined effects of bed thermal expansions and coolant pressure

Fatollah Tehranian, Reem Hejal

Fusion Engineering and Design > 1995 > 27 > 290-296

In Part I of this study, a model representing the thermomechanical response of a particle bed-structural wall system in a layered configuration, subjected to both a bed temperature rise and an external coolant pressure, was presented. The results of a parametric study, based on the developed model, on the effect of the bed thermal expansions alone on a beryllium particle bed-stainless system were...

article

Initial liquid metal magnetohydrodynamic thin film flow experiments in the MeGA-loop facility at UCLA

Neil B. Morley, Alexander A. Gaizer, Mark S. Tillack, Mohamed A. Abdou

Fusion Engineering and Design > 1995 > 27 > 725-730

Free surface, thin film flows of liquid metal were investigated experimentally in the presence of a coplanar magnetic field. This investigation was performed in a new magnetohydrodynamic (MHD) flow facility, the MeGA-loop, utilizing a low melting temperature lead-bismuth alloy as the working metal. Owing to the relatively low magnetic field produced by the present field coil system, the ordinary...

article

Thermal conductivity of a beryllium gas packed bed

Mingjie Xu, Mohamed A. Abdou, A. Rene Raffray

Fusion Engineering and Design > 1995 > 27 > 240-246

An unsintered packed bed has been suggested as a material form for the solid breeder and multiplier in fusion reactor blankets. Study of the effective bed thermal conductivity can provide tools for analysis of the blanket performance under different operating conditions, and for analysis of how to control actively the thermal behavior of the blanket. Issues of particular interest are the ability...

article

Flow balancing in liquid metal blankets

M.S. Tillack, N.B. Morley

Fusion Engineering and Design > 1995 > 27 > 735-741

Non-uniform flow distribution between parallel channels is one of the most serious concerns for self-cooled liquid metal blankets with electrically insulated walls. We show that uncertainties in flow distribution can be dramatically reduced by relatively simple design modifications. Several design features which impose flow uniformity by electrically coupling parallel channels are surveyed. Basic...

article

Thermal and mechanical properties of beryllium pebbles

Etsuo Ishitsuka, Hiroshi Kawamura

Fusion Engineering and Design > 1995 > 27 > 263-268

A low impurity and low cost pebble production method has been developed using an improved rotating electrode, and basic characteristics of the beryllium pebbles have been measured. Thermal expansion coefficient and specific heat of the unirradiated pebble samples were measured by laser interferometry and differential scanning calorimetry respectively. These thermal properties are almost identical...

article

ITER: the first experimental fusion reactor

ITER Joint Central Team and Home Teams, P.-H. Rebut

Fusion Engineering and Design > 1995 > 27 > 3-16

The International Thermonuclear Experimental Reactor (ITER) Project is a multi-phased project, presently proceeding under the auspices of the International Atomic Energy Agency according to the terms of a four-party agreement between the European Atomic Energy Community, the Government of Japan, the Government of the United States, and the Government of the Russian Federation. The project is based...

article

Design and life assessment of first wall components

E. Diegele, D. Munz, G. Rizzi

Fusion Engineering and Design > 1995 > 27 > 210-215

The first wall (FW) of a tokamak fusion reactor is subjected to periodically changing large heat fluxes. Water-cooled FW panels made from austenitic SS 316 L steel are analyzed. First, life predictions for initially defect-free components, obtained by applying design code rules, are compared with experimental results. It is shown that designing by code is very conservative under thermal fatigue...

Publication date

Set your own date range

Year

2018 (45)
2017 (818)
2016 (642)
2015 (662)
2014 (531)
2013 (650)
2012 (390)
2011 (633)
2010 (422)
2009 (431)
2008 (344)
2007 (401)
2006 (427)
2005 (400)
2004 (96)
2003 (384)
2002 (270)
2001 (548)
2000 (352)
1999 (208)
1998 (319)
1997 (278)
1996 (111)
1995 (319)
more

Content availability

Available (9,262)
None (419)

Keywords

ITER (1,316)
TOKAMAK (364)
TRITIUM (306)
DIVERTOR (286)
DEMO (280)
FUSION (278)
TUNGSTEN (227)
REMOTE HANDLING (202)
BLANKET (195)
IFMIF (173)
JET (157)
DATA ACQUISITION (156)
NEUTRONICS (134)
WENDELSTEIN 7-X (127)
BERYLLIUM (125)
VACUUM VESSEL (120)
FUSION REACTOR (119)
FIRST WALL (118)
TBM (117)
PLASMA FACING COMPONENTS (114)
LITHIUM (113)
SAFETY (102)
NUCLEAR FUSION (97)
PLASMA (97)
STELLARATOR (96)
JT-60SA (92)
DESIGN (91)
KSTAR (91)
EAST (89)
MCNP (86)
PLASMA CONTROL (86)
BREEDING BLANKET (85)
DIAGNOSTICS (85)
TEST BLANKET MODULE (83)
GYROTRON (71)
REAL-TIME (71)
MAINTENANCE (68)
ECRH (67)
CONTROL (65)
HYDROGEN (64)
MICROSTRUCTURE (63)
TORE SUPRA (62)
HIGH HEAT FLUX (61)
NEUTRON IRRADIATION (60)
LIQUID METAL (58)
MHD (58)
PLASMA FACING COMPONENT (58)
W7-X (57)
ASDEX UPGRADE (56)
LHD (54)
MDSPLUS (54)
POWER SUPPLY (54)
ACTIVATION (53)
NEUTRAL BEAM INJECTOR (53)
CFD (51)
EPICS (50)
HEAT TRANSFER (50)
STRUCTURAL ANALYSIS (49)
NEUTRAL BEAM (48)
REMOTE PARTICIPATION (48)
VACUUM (48)
NEUTRAL BEAM INJECTION (47)
CFETR (46)
DEUTERIUM (46)
SIMULATION (45)
LIQUID LITHIUM (44)
CONTROL SYSTEM (43)
HELIUM (43)
MECHANICAL PROPERTIES (43)
SUPERCONDUCTING MAGNET (43)
NUMERICAL SIMULATION (42)
THERMAL CONDUCTIVITY (42)
FUSION POWER PLANT (41)
MONTE CARLO (41)
CORROSION (40)
FPGA (40)
ICRF (40)
ICRH (40)
PERMEATION (40)
IRRADIATION (39)
NBI (39)
REAL-TIME CONTROL (39)
EROSION (38)
PEBBLE BED (38)
PLASMA DIAGNOSTICS (38)
DATABASE (37)
CRYOSTAT (36)
HCPB (36)
RADIATION DAMAGE (36)
FINITE ELEMENT ANALYSIS (35)
AVAILABILITY (34)
DIFFUSION (34)
EUROFER (34)
MAGNETIC FIELD (34)
PLASMA-FACING COMPONENTS (34)
ANALYSIS (33)
COPPER (33)
HCLL (33)
NEUTRON (33)
FUEL CYCLE (32)
more

INFONA - science communication portal

Fusion Engineering and Design

The tubular separate first wall for ITER-EDA

Analysis of the tokamak volumetric neutron source (VNS) design and range of its parameters

Impact of JET experimental results and engineering development on the definition of the ITER design concept

MHD flow in rectangular ducts with inclined non-uniform transverse magnetic field

Development of a direct insulation layer for a self-cooled liquid metal fusion reactor blanket

Dynamic behavior of fusion structural components under strong magnetic fields

Impact of the passive stabilization system on the dynamic loads of the ITER first wall/blanket during a plasma disruption event

Disruption problematics in segmented-blanket concepts

Cracking susceptibility of stainless steel subjected to plasma disruption

Transient thermal and dynamic stresses in strongback-design blankets

Helium induced swelling and tritium trapping mechanisms in irradiated beryllium: a comprehensive approach

Reduction of toroidal ripple by using high T _c superconductors

A European proposal for an ITER water-cooled solid breeder blanket

Thermomechanical interaction of particle bed-structural wall in a layered configuration Part II: Combined effects of bed thermal expansions and coolant pressure

Initial liquid metal magnetohydrodynamic thin film flow experiments in the MeGA-loop facility at UCLA

Thermal conductivity of a beryllium gas packed bed

Flow balancing in liquid metal blankets

Thermal and mechanical properties of beryllium pebbles

ITER: the first experimental fusion reactor

Design and life assessment of first wall components

Filter options

Publication date

Year

Content availability

Keywords

INFONA - science communication portal

Fusion Engineering and Design

Add recipient

Sending message cancelled

Are you sure you want to cancel sending this message?

Send message

Filter options

Publication date

Date range setting

Set the date range to filter the displayed results. You can set a starting date, ending date or both. You can enter the dates manually or choose them from the calendar.

Year

Content availability

Keywords

Reporting an error / abuse

Sending the report failed

Accessibility options