Lay-out activities for the IFMIF high flux test module
| Autor: | Ulrich Fischer, V. Slobodtchouk, K Schleisiek, B. Dolensky, S. Gordeev, Stanislav Simakov, E. Stratmanns, Volker Heinzel |
|---|---|
| Rok vydání: | 2002 |
| Předmět: |
Materials science
Mechanical Engineering Nuclear engineering chemistry.chemical_element Nuclear reactor Fusion power Ellipsoid law.invention Thermal hydraulics High flux Nuclear Energy and Engineering chemistry Volume (thermodynamics) law Heat transfer General Materials Science Helium Civil and Structural Engineering |
| Zdroj: | Fusion Engineering and Design. :47-52 |
| ISSN: | 0920-3796 |
| DOI: | 10.1016/s0920-3796(02)00237-5 |
| Popis: | Nuclear and thermal–hydraulic analyses have been performed with the objective to further optimise the high-flux-test-module (HFTM) design. The nuclear analyses showed that the volume of 0.5 l with a damage rate dpa/fpy>20 can be achieved, if the HFTM has a contour like a semi ellipsoid. The thermal–hydraulic analyses focused on the experimental validation of the helium cooling concept. Integral heat transfer experiments revealed that the specimens can be kept at temperatures up to 600 °C. Dedicated experiments are being designed with the objective to provide data for the validation of the direct numeric FE simulation of the helium flow field, the heat transfer and the pressure losses. |
| Databáze: | OpenAIRE |
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