Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000079" target="_blank" >RIV/26722445:_____/19:N0000079 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/abs/pii/S0920379619300080" target="_blank" >https://www.sciencedirect.com/science/article/abs/pii/S0920379619300080</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.fusengdes.2019.01.008" target="_blank" >10.1016/j.fusengdes.2019.01.008</a>
Alternative languages
Result language
angličtina
Original language name
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts
Original language description
Fusion reactors represent a future evolution of the nuclear technology improving the world-wide energy portfolio. The experimental fusion reactor under construction (ITER) and the planned industrial fusion reactors (DEMO) are large and complex facilities. For their operation it is necessary to ensure safety limiting of radiological and mobilizable source terms inventory, such as tritium and radioactive dust. The source term inventories shall be assumed in the establishment of operational and safety requirements for DEMO, as well as performing safety analyses for commercial fusion devices. In the last few years a methodology for evaluation of tritium and dust source term inventory has been proposed in the framework of the EUROFusion project. The basis of the methodology is a semi-empirical approach to scale the radioactive inventory limits implemented in ITER. The source term amounts derived for DEMO will supply a guidance for safe operation of future fusion reactors. The development of methodology has to be completed and refined because of the lack of validation versus adequate experimental data and rules for extension to different scenarios. The aim of this work is assessment of the developed methodology for evaluation of the source terms inventory versus JET operating limits for tritium and versus the dust control strategy adopted in ITER for the dust. The updating of the methodology for the dust and T inventory was carried out in line with the current DEMO design. The new values of the in-VV source terms were achieved. These values are recommended to be used for the safety assessment of the fusion reactor. Calculated DST and TST inventories' values show a reasonable agreement with scaled ITER or assessed JET limits.
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)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2019
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
146
Issue of the periodical within the volume
September
Country of publishing house
CH - SWITZERLAND
Number of pages
4
Pages from-to
510-513
UT code for WoS article
000488307400113
EID of the result in the Scopus database
2-s2.0-85060898109