Critical Heat Flux in Subcooled Water Flow of One-Side-Heated Screw Tubes

Boscary, J.; Araki, M.; Suzuki, Satoshi; Ezato, Koichiro; Akiba, Masato

doi:10.13182/fst99-a82

Cited by 23 publications

(15 citation statements)

References 2 publications

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“…Heat removal capabilities have already been confirmed, comparable with those of the twisted tape (swirl tube). 77) Metallographic observation showed fatigue-cracks initiated from the outer surface of the tube and propagated towards the inner surface. Although stress concentration and crack initiation at the root of the internal fins were concerned in this concept, the results indicated that the fins had no dominant effect on their fatigue lifetimes.…”

Section: Iter Relevant High Heat Flux Testing On Plasma Facing Surfacmentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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Section: Iter Relevant High Heat Flux Testing On Plasma Facing Surfacmentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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“…To investigate the heat removal limits at higher temperature and pressure range than those at the previous campaign [7], CHF experiments were carried out at inlet temperature of 30 and 100 • C and at the local pressure of 2 and 4 MPa. U ax ranges from 14 to 3 m/s.…”

Section: Methodsmentioning

confidence: 99%

“…In the present work, M10 thread type with the pitch of 1.5 mm is used because it is experimentally confirmed to have the highest incident critical heat flux (ICHF) among the other screw tubes with the different geometries in Ref. [7]. Major dimensions of M10 thread are as following; the minimum and maximum inner diameters are 8.38 and 10 mm, respectively, and the fin height is 0.81 mm.…”

Section: Screw Tube Sample For Heat Transfer Testmentioning

confidence: 99%

“…Since the fin can be machined by a simple threading, this tube is called a screw tube. In our previous experiments, it was found that heat removal performance of the screw tube is twice as high as that of a smooth tube [7]. The nut-like inner surface can work as a combination of enlargement of heat transfer area and turbulence promoter of cooling water near the surface to enhance heat transfer.…”

Section: Introductionmentioning

confidence: 99%

“…To increase CHF, it is possible to make use of several techniques, namely swirl flow [3], helically coiled wires [4] and hypervapotron effect [5]. A cooling tube with a helical triangular fin on its inner surface like a nut has been proposed [6,7]. Since the fin can be machined by a simple threading, this tube is called a screw tube.…”

Section: Introductionmentioning

confidence: 99%

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