HELCZA - High heat flux test facility for testing ITER EU first wall components
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000011" target="_blank" >RIV/26722445:_____/17:N0000011 - isvavai.cz</a>
Alternative codes found
RIV/61389021:_____/17:00480958
Result on the web
<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.059" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2017.03.059</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.059" target="_blank" >10.1016/j.fusengdes.2017.03.059</a>
Alternative languages
Result language
angličtina
Original language name
HELCZA - High heat flux test facility for testing ITER EU first wall components
Original language description
The ITER first wall panels are exposed directly to thermonuclear plasma and must extract heat loads of approximately 2 MW/m2 (normal heat flux) to 4.7 MW/m2 (enhanced heat flux). The panels are qualified through high heat flux cyclic testing before installation in ITER. Initially, the first wall panel prototypes will undergo full-power tests, they will be followed by the pre-series panels and finally the series ones. The experimental complex HELCZA (High Energy Load CZech Assembly) has been completed and is currently in the commissioning phase. HELCZA shall be optimised to provide a cyclic heating of the ITER EU first wall panels with a heat flux in the multi-MW/m2 range using an 800 kW electron beam. On a reduced area it is possible to reach GW/m2 scale. Total available test area in HELCZA is 4 m2 depending on the experimental setup. Operational conditions of the HELCZA facility enable the temperature of the cooling water to be set between 25 °C and 320 °C, within a pressure range up to 15 MPa. The cooling system provides an optimal flow rate up to 40 m3/h independent of the pressure.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
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)
Others
Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Fusion Engineering and Design
ISSN
0920-3796
e-ISSN
1873-7196
Volume of the periodical
124
Issue of the periodical within the volume
November
Country of publishing house
CH - SWITZERLAND
Number of pages
4
Pages from-to
187-190
UT code for WoS article
000419411900040
EID of the result in the Scopus database
2-s2.0-85015782575