Assessment of hypervapotron heat sink performance using CFD under DEMO relevant first wall conditions

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000182" target="_blank" >RIV/26722445:_____/16:N0000182 - isvavai.cz</a>

Result on the web

<a href="http://dx.doi.org/10.1016/j.fusengdes.2016.03.044" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2016.03.044</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2016.03.044" target="_blank" >10.1016/j.fusengdes.2016.03.044</a>

Result language

angličtina

Original language name

Assessment of hypervapotron heat sink performance using CFD under DEMO relevant first wall conditions

Original language description

Among the proposed First Wall (FW) cooling concepts for European Demonstration Fusion Power Plant (DEMO), water cooled FW is one of the options. The heat flux load distribution on the FW of the DEMO reactor is not yet precisely defined. But if the heat loads on the FW are extrapolated from ITER conditions, the numbers are quite high and have to be handled none the less. The design of the FW itself is challenging as the thermal conductivity ratio of heat sink materials in ITER (CuCrZr) and in DEMO (Eurofer 97) is similar to 10-12 and the operating conditions are of Pressurized Water Reactor (PWR) in DEMO instead of 70 degrees C and 4 MPa as in ITER. This paper analyzes the performance of Hypervapotron (HV) heat sink for FW limiter application under DEMO conditions. Where different materials, temperatures, heat fluxes and velocities are considered to predict the performance of the HV, to establish its limits in handling the heat loads before reaching the upper limits from temperature point of view. In order to assess the performance, numerical simulations are performed using commercial CFD code, which was previously validated in predicting the thermal hydraulic performance of HV geometry. Based on the results the potential usage of HV heat sink for DEMO will be assessed.

Czech name

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Czech description

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Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2016

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Name of the periodical

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

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Volume of the periodical

109-111A

Issue of the periodical within the volume

November

Country of publishing house

CH - SWITZERLAND

Number of pages

5

Pages from-to

109-113

UT code for WoS article

000382421900020

EID of the result in the Scopus database

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