Experiments and numerical analysis of eddy currents in the first wall of a fusion reactor

1990 ◽  
Vol 26 (2) ◽  
pp. 869-872 ◽  
Author(s):  
M. Hashimoto ◽  
H. Hashizume ◽  
T. Sugiura ◽  
T. Takagi ◽  
K. Miya ◽  
...  
Keyword(s):  
Numerical Analysis ◽  
Eddy Currents ◽  
Fusion Reactor ◽  
First Wall

scholarly journals Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code

2021 ◽  
Vol 12 (1) ◽  
pp. 187
Author(s):  
Michela Angelucci ◽  
Bruno Gonfiotti ◽  
Bradut-Eugen Ghidersa ◽  
Xue Zhou Jin ◽  
Mihaela Ionescu-Bujor ◽  
...  
Keyword(s):  
Experimental Data ◽  
Numerical Analysis ◽  
Fusion Reactor ◽  
Numerical Analyses ◽  
Main Concern ◽  
First Wall ◽  
Pebble Bed ◽  
Experimental Campaign ◽  
Post Test ◽  
Numerical Tools

The validation of numerical tools employed in the analysis of incidental transients in a fusion reactor is a topic of main concern. KIT is taking part in this task providing both experimental data and by performing numerical analysis in support of the main codes used for the safety analyses of the Helium Cooled Pebble Bed (HCPB) blanket concept. In recent years, an experimental campaign has been performed in the KIT-HELOKA facility to investigate the behavior of a First Wall Mock-Up (FWMU) under Loss Of Flow Accident (LOFA) conditions. The aim of the experimental campaign was twofold: to check the expected DEMO thermal-hydraulics conditions during normal and off-normal conditions and to provide robust data for code validation. The present work is part of these validation efforts, and it deals with the analysis of the LOFA experimental campaign with the system code MELCOR 1.8.6 for fusion. A best-estimate methodology has been used in support of this analysis to ease the distinction between user’s assumptions and code limitations. The numerical analyses are here described together with their goals, achievements, and lesson learnt.

Alignment of small He-Bubbles during in situ deformation of Al-foils

1978 ◽  
Vol 36 (1) ◽  
pp. 396-397
Author(s):  
E. Ruedl ◽  
P. Schiller
Keyword(s):  
Fusion Reactor ◽  
Matrix Material ◽  
Fusion Reactors ◽  
First Wall ◽  
Potential Matrix ◽  
In Situ Deformation ◽  
Α Particles ◽  
Metal Aluminium

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.

Numerical analysis of supersonic jet flow and dust transport induced by air ingress in a fusion reactor

2021 ◽  
Vol 32 (7) ◽  
Author(s):  
Bu-Er Wang ◽  
Shi-Chao Zhang ◽  
Zhen Wang ◽  
Jiang-Tao Jia ◽  
Zhi-Bin Chen
Keyword(s):  
Numerical Analysis ◽  
Fusion Reactor ◽  
Supersonic Jet ◽  
Jet Flow ◽  
Dust Transport ◽  
Air Ingress

Special Features of First-Wall Heat Transfer in Liquid-Metal Fusion Reactor Blankets

1987 ◽  
Vol 12 (1) ◽  
pp. 104-113 ◽  
Author(s):  
K. Taghavi ◽  
M. S. Tillack ◽  
H. Madarame
Keyword(s):  
Heat Transfer ◽  
Liquid Metal ◽  
Fusion Reactor ◽  
Wall Heat Transfer ◽  
First Wall

Updated Design and Development Route for CH HCCB TBM and its Mockup

2013 ◽  
Author(s):  
Gang Hu ◽  
Kaiming Feng ◽  
Zhou Zhao ◽  
Guoshu Zhang ◽  
Qijie Wang ◽  
...  
Keyword(s):  
Fusion Reactor ◽  
Surface Heat ◽  
Maximum Temperature ◽  
First Wall ◽  
Total Stress ◽  
Design And Development ◽  
Tritium Production ◽  
Radial Length ◽  
Development Route ◽  
Purge Gas

Chinese helium-cooled ceramics breeder test blanket module (CH HCCB TBM) is determined to be tested in ITER machine to get data for fusion reactor design and development in future. Chinese TBM is designed to occupy half of port C with 484mm in torroidal and 1660mm in poloidal. Radial length is 675mm. TBM is composed of box, 12 submodules and independent backplate. Box formed by first wall, grids and caps have 12 caivities to hold submodules. Box and submodules are supported by backplate by welding. Backplate distribute helium with flow rate 1.36kg/s to cool first wall and then part of it go out of TBM by bypass. The rest 0.77kg/s go on to cool caps and girds first and then cool submodules. Submodules with dimensions 250mm×202mm×318mm have independent cooling and purging systems connected to backplate manifold systems. In a submodule, two U-shaped structures hold breeding material Li4SiO4 pebbles. Out of the structure filled beryllium pebbles. Neutronics results show that tritium production is ∼64mg/FPD. Maximum temperature 538°C of structure material occurs in the front of first wall with surface heat flux 0.5MW/m2. Maximum total stress at first wall is 471MPa at 394°C; that in submodules is 426MPa at 400°C; that in backplate is 526MPa at 410°C, In order to explore development technologies for the TBM, a mockup with dimensions 484mm (torroidal)×592mm (poloidal)×675mm (radial) has been designed. The mockup with similar structure ignores bypass and purge gas systems. In the mockup, there’s only one submodule and the other three are replaced by submodule replacements. By discussions and investigations, development route has been decided and the mockup is being fabricated.

scholarly journals Overall Evaluation for Graphites as First Wall Material of a Fusion Reactor

TANSO ◽  
1991 ◽  
Vol 1991 (150) ◽  
pp. 354-364 ◽  
Author(s):  
Toshiro Yamashina ◽  
Tomoaki Hino
Keyword(s):  
Fusion Reactor ◽  
Wall Material ◽  
First Wall ◽  
Overall Evaluation

Investigation of cascade-type falling liquid-film along first wall of laser-fusion reactor

2008 ◽  
Vol 83 (10-12) ◽  
pp. 1888-1892 ◽  
Author(s):  
T. Kunugi ◽  
T. Nakai ◽  
Z. Kawara ◽  
T. Norimatsu ◽  
Y. Kozaki
Keyword(s):  
Liquid Film ◽  
Fusion Reactor ◽  
Laser Fusion ◽  
First Wall ◽  
Falling Liquid Film ◽  
Cascade Type

Atomistic modeling of diffusion coefficient in fusion reactor first wall material tungsten

2014 ◽  
Vol 73 (1) ◽  
pp. 111-115 ◽  
Author(s):  
Zenghui Wang ◽  
Kaixuan Zhao ◽  
Weiming Chen ◽  
Xiaodi Chen ◽  
Longyan Zhang
Keyword(s):  
Diffusion Coefficient ◽  
Fusion Reactor ◽  
Wall Material ◽  
Atomistic Modeling ◽  
First Wall
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