Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000053" target="_blank" >RIV/26722445:_____/18:N0000053 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/pii/S0920379618305040" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379618305040</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.fusengdes.2018.05.072" target="_blank" >10.1016/j.fusengdes.2018.05.072</a>
Alternative languages
Result language
angličtina
Original language name
Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
Original language description
The European DEMOnstration (DEMO) reactor precedes the development of the fully commercial fusion power plant. One of the key components of the DEMO is the first wall (FW). The FW is acted upon by extreme particle and radiation loads, which results in high heat fluxes varying across the reactor vessel. This paper attempts to evaluate two DEMO FW water cooling concepts from the stress point of view. The heat sink material chosen for the FW is Eurofer97 with thermal conductivity of similar to 28 W/mK at 20 degrees C; the cooling conditions opted are those of pressurized water reactor (PWR), i.e. 285 degrees C and 15.5 MPa. In the present work it is attempted to perform the stress analysis of the two different heat sink channel configurations, these are circular pipes with countercurrent flow and channel with hypervapotron configuration. The thermo-hydraulic optimization of these components has been performed in one of the author's previous work. The stress in the components is caused by the pressure of the fluid and increase in the temperature of the material. To accomplish the work, commercial finite element method software ANSYS is used. In a case of unsatisfactory results, further recommendations are given. Simulations are performed with P91, which is material being commonly used in power engineering and will be also used for manufacturing of the discussed configuration of DEMO FW mock-ups which will be afterwards tested in high heat flux facility HELCZA.
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
<a href="/en/project/LQ1603" target="_blank" >LQ1603: Research for SUSEN</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2018
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
136
Issue of the periodical within the volume
SI
Country of publishing house
CH - SWITZERLAND
Number of pages
6
Pages from-to
1618-1623
UT code for WoS article
000452575300142
EID of the result in the Scopus database
2-s2.0-85048419241