HETS performances in He cooled power plant divertor

Pizzuto, A.; Karditsas, P.J.; Nardi, C.; Papastergiou, S.

doi:10.1016/j.fusengdes.2005.06.008

Cited by 8 publications

(5 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Convective heat transfer coefficients produced by this method are over three times those achievable in parallel wall flow concepts, at equivalent flow speeds [20]. Though considered for the HETS concept [10,21], the majority of DEMO divertor proposals employing jet impingement are focused around the use of helium as a coolant [7,10,14] and tungsten as a structural material.…”

Section: A High-heat Flux Heat Sink Modulementioning

confidence: 99%

Development of a heat sink module for a near-term DEMO divertor

Nicholas

Ireland

Hancock

et al. 2018

Fusion Engineering and Design

View full text Add to dashboard Cite

Section: A High-heat Flux Heat Sink Modulementioning

confidence: 99%

Development of a heat sink module for a near-term DEMO divertor

Nicholas

Ireland

Hancock

et al. 2018

Fusion Engineering and Design

View full text Add to dashboard Cite

“…The HETS design (ENEA). The HETS concept [3], initially developed for water, has been extended in the past years for the use of He as a coolant. Studies have been performed to evaluate its suitability in such an environment.…”

Section: Basic Design Featuresmentioning

confidence: 99%

“…Since 2002 modular divertors have been designed, which help reduce the thermal stresses. Two modular divertor concepts are being pursued within the current PPCS [2]: the ENEA concept HETS (Highefficiency thermal shield) [3] and the FZK concept HEMJ (Hecooled divertor with multiple jet cooling) [4] which has been further developed as an alternative to the forerunner design variants HEMP/HEMS [5,6] (He-cooled modular divertor with integrated pin/slot array).…”

Section: Introductionmentioning

confidence: 99%

European development of He-cooled divertors for fusion power plants

et al. 2005

View full text Add to dashboard Cite

Helium-cooled divertor concepts are considered suitable for use in fusion power plants for safety reasons, as they enable the use of a coolant compatible with any blanket concept, since water would not be acceptable, e.g. in connection with ceramic breeder blankets using large amounts of beryllium. Moreover, they allow for a high coolant exit temperature for increasing the efficiency of the power conversion system. Within the framework of the European power plant conceptual study, different helium-cooled divertor concepts based on different heat transfer mechanisms are being investigated at ENEA Frascati, Italy, and Forschungszentrum Karlsruhe, Germany. They are based on a modular design which helps reduce thermal stresses. The design goal is to withstand a high heat flux of about 10–15 MW m−2, a value which is considered relevant to future fusion power plants to be built after ITER. The development and optimization of the divertor concepts require an iterative design approach with analyses, studies of materials and fabrication technologies and the execution of experiments. These issues and the state of the art of divertor development shall be the subject of this report.

show abstract

“…This concept is based on elements joined in series and protected by a hemispheric dome; it allows an increase of exchange coefficients both for high speed of gas and for "jet impingement" effects of gas coming out from the internal side of hemispheric dome. Calculation shows the possibility to withstand thermal fluxes up to 10 MW/m 2 , using W as structural material [2][3][4]. Anyway experimental tests are requested, aimed at both to verify thermal exchange coefficients and to verify the compatibility of the pressure drops with the divertor specification.…”

Section: Introductionmentioning

confidence: 99%