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ABSTRACT: Recent progress on the development of new divertor high heat flux
components in JAERI is presented in this paper. Large-scale divertor
mock-ups, 90 cm long×40 cm wide with carbon fiber composite
armors, were fabricated and tested. The mock-ups withstood a heat load
of 5 MW/m<sup>2</sup> for more than 3000 cycles, and 20 MW/m<sup>2</sup>
for 1000 cycles. A small mock-up made of reduced activation ferritic
steel without armors was also fabricated and tested. The mock-up endured
a heat load of 5 MW/m<sup>2</sup> for 10,000 cycles
Fusion Engineering, 1999. 18th Symposium on; 02/1999
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ABSTRACT: Recent progress on the development of new divertor high heat flux
components in JAERI is presented in this paper. Small-scale divertor
mock-up was tested in PBEF (Particle Beam Engineering Facility). The
mock-up has armor tiles made of 3D carbon-fiber-reinforced carbon
composite (CFC) brazed onto a cooling tube made of
dispersion-strengthened copper (DSCu) with a silver-free material. In
the thermal cycling experiment, the mock-up could survive from the
cyclic thermal load of 20 MW/m<sup>2</sup>. In addition, the divertor
mock-up with CVD-W armors also could survive from the cyclic thermal
load of 5 MW/m<sup>2</sup> for 1000 cycles. For the development of
real-scale divertor mockups, the real-scale vertical target mock-ups
were successfully developed and tested. The armor tiles were made of
unidirectional CFC and the cooling tube was made of DSCu. At a heat flux
of 20 MW/m<sup>2</sup>, the mock-up with DSCu cooling tube could
withstand 1,000 thermal cycles without any evidence of thermal fatigue
of the cooling tube
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium; 11/1997
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K. Nakamura,
M. Akiba, S. Suzuki,
K. Satoh,
K. Yokoyama,
M. Dairaku,
M. Araki,
Y. Ohara,
T. Inoue,
Y. Okumura,
I. Smid
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ABSTRACT: To develop plasma facing components (PFC) for the next fusion
devices, JAERI has been carrying out high heat flux and high particle
flux experiments on the divertor modules and candidate materials in
JAERI Electron Beam Irradiation System (JEBIS). (1) To investigate the
feasibility and the advantage of a saddle type divertor modules, which
has unidirectional (1-D) carbon fiber reinforced carbon composites
(CFCs) armour tile brazed on OFHC-copper heat sink, high heat flux
experiments have been carried out under a cyclic heat load of 24.5 MW/m
<sup>2</sup> at a duration of 30 s. After 1000 cycles, no degradation of
thermal response and no defect in the module was found. (2) To reduce
the residual stress around the brazed interface, we have developed small
specimens with the new materials combination of W-30Cu composites heat
sink and 1-D CFC armour tile and carried out the high heat flux
experiments under a cyclic heat load of 15 MW/m<sup>2</sup> at a
duration of 20 s. After 1,000 cycles, no cracks have been observed at
the interface. (3) To evaluate the erosion of armour tiles by high heat
flux, we have measured the erosion of CFCs and isotropic graphite up to
1100°C under a heat flux of 1800 MW/m<sup>2</sup> for the duration
of 1.5~2 ms. It is clear that the erosion of carbon based materials
increases with the bulk temperature and decreases with the thermal
conductivity. (4) To evaluate the erosion by high particle flux, we have
developed a new irradiation device, which have a high hydrogen particle
flux of 10<sup>21</sup>/m<sup>2</sup>/s at 50~100 eV
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on; 11/1993
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ABSTRACT: Plasma Facing Components will be exposed to severe heat loads
during the normal operation, and will severely be eroded by evaporation
and particle emission during disruptions in next generation fusion
devices such as International Thermonuclear Experimental Reactor (ITER).
In this paper, we present recent major R&D topics on plasma facing
components (PFCs) at JAERI as follows; (1) thermal cycling experiments
on a 1 m long divertor mock-up, (2) disruption simulation tests on
B<sub>4</sub>C doped CFCs and tungsten, (3) tensile and bending tests of
beryllium/copper alloy duplex structures
Fusion Engineering, 1995. SOFE '95. 'Seeking a New Energy Era'., 16th IEEE/NPSS Symposium;
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ABSTRACT: In the International Thermonuclear Experimental Reactor (ITER), the divertor high heat-flux components are subjected not to only severe heat and particle loads, but also to large electromagnetic loads during reactor operation. A great deal of R&D has been carried out throughout the world with regard to the design of robust high heat-flux components. Based on R&D results, small and intermediate size mock-ups constructed from various armor tile materials have been successfully developed with respect to a thermomechanical point of view. However, little analysis has been carried out with regard to the elastic stresses induced with in the high heat-flux components via the electromagnetic loads during a plasma disruption. Furthermore, past research has only considered thermomechanical and electromagnetic loadings separately and uncoupled. Therefore, a systematic analysis of the combined effects of thermomechanical and electromagnetic loadings has been performed, with the analytical results assessed by ASME section 3 evaluation code.
Fusion Engineering and Design.
