Thermal hydraulics of water cooled divertors

Baxi, C.B.

doi:10.1016/s0920-3796(01)00258-7

Cited by 18 publications

(4 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Actually this parameter seems to constitute one of the main differences between nowadays ITER divertor, and DEMO divertor requirements [5]. Main DEMO design parameters and requirements which impact the divertor design are listed in [3] [4]. The peak incident heat flux is one of the "most significant" parameters, because it will determine the thermal gradient (and relevant thermal stresses) in the plasma facing wall.…”

Section: Requirements and Assumptionsmentioning

confidence: 99%

Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor

Richou

Gallay

Chu

et al. 2017

Fusion Engineering and Design

View full text Add to dashboard Cite

The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. In DEMO, divertor target must survive an environment of high heat fluxes (~Up to 20 MW/m² during transient) and neutron irradiation. This paper presents an advanced actively cooled concept aiming to reduce the thermal stress at the bond interface due to distinct difference in thermal expansion between tungsten and CuCrZr which may cause a mismatch during thermal cycling. This concept is based on the use of a W/Cu functionally graded material (FGM) interlayer instead of the copper interlayer. Mock-up geometrical definition was performed based on available technology to manufacture FGM in a monoblock configuration, with regard to Eurofusion divertor DEMO project specifications and minimizing as much as possible thermomechanical stresses during operation. The interlayer (~25 µm) is made with PVD (Plasma Vapor deposition) and composed of continuous gradient of W from 100% at the interior part of the tile to 0% at the external part while Cu varies from 0% to 100%. Hot isotactic pressure is realized to assemble the CuCrZr tube to W tile equipped with graded material. With Infrared (SATIR) and US nondestructive examinations, mock-ups show good interface quality. Relevancy of low thickness FGM as a bonding solution between armour and structural materials for divertor application will be checked in a near term future with high heat flux tests.

show abstract

Section: Requirements and Assumptionsmentioning

confidence: 99%

Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor

Richou

Gallay

Chu

et al. 2017

Fusion Engineering and Design

View full text Add to dashboard Cite

show abstract

“…The tests conducted at SNL showed that ICHF = 24.5 MW/m 2 is obtained with water flowing at 4 MPa, 100°C, 10 m/s, with a pressure drop of 0.19 MPa/m [27]. Erosion and corrosion of the porous coating has kept this method from wide acceptance [28].…”

Section: Water Coolingmentioning

confidence: 99%

Comparison of Cooling Schemes for High Heat Flux Components Cooling in Fusion Reactors

Domalapally

Entler

2015

Acta Polytech

View full text Add to dashboard Cite

show abstract

“…The heat transfer coefficient was calculated as a function of local wall temperature by correlations described in Ref. [5]. These correlations take into consideration the temperature dependence of the heat transfer coefficient, the temperature for incipient boiling, and sub-cooled nucleate boiling in forced convection.…”

Section: Thermal Stress Analysismentioning

confidence: 99%