Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000002" target="_blank" >RIV/26722445:_____/16:N0000002 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.fusengdes.2016.01.052" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2016.01.052</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2016.01.052" target="_blank" >10.1016/j.fusengdes.2016.01.052</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Popis výsledku v původním jazyce

The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing. (C) 2016 EURATOM/CCFE Fusion Association.

Název v anglickém jazyce

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Popis výsledku anglicky

The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing. (C) 2016 EURATOM/CCFE Fusion Association.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/8D15001" target="_blank" >8D15001: Project ID 633053 - EUROfusion</a><br>

Návaznosti

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

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název periodika

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

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Svazek periodika

109-111A

Číslo periodika v rámci svazku

November

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

8

Strana od-do

917-924

Kód UT WoS článku

000382421900158

EID výsledku v databázi Scopus

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