Numerical Analyses for Conceptual Design of an Irradiation PbLi Capsule for Testing of Protective Coatings for the European DEMO Breeding Blanket Project

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000169" target="_blank" >RIV/26722445:_____/18:N0000169 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/abs/pii/S0920379618302977" target="_blank" >https://www.sciencedirect.com/science/article/abs/pii/S0920379618302977</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2018.04.011" target="_blank" >10.1016/j.fusengdes.2018.04.011</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Numerical Analyses for Conceptual Design of an Irradiation PbLi Capsule for Testing of Protective Coatings for the European DEMO Breeding Blanket Project

Popis výsledku v původním jazyce

Three concepts of the European DEMO Breeding Blankets currently under development within the EUROfusion project use as a breeder eutectic lithium-lead (PbLi). Since the inner walls of the blanket modules and the associated ancillary systems has to withstand severe corrosion attack, protective aluminum-based corrosion and tritium permeation barriers are being developed within the Breeding Blanket project. The goal of this activity is to evaluate properties of these protective coatings in conditions of a combined effect of hot PbLi and neutron irradiation from the LVR-15 reactor. The reduction effect of coatings on tritium permeation will be measured comparing the tritium permeation rate between coated and uncoated Eurofer samples. The paper presents the major results of the preliminary neutronics and thermal-hydraulics calculations leading to the proper design of the irradiation capsule which is also described in this paper.

Název v anglickém jazyce

Numerical Analyses for Conceptual Design of an Irradiation PbLi Capsule for Testing of Protective Coatings for the European DEMO Breeding Blanket Project

Popis výsledku anglicky

Three concepts of the European DEMO Breeding Blankets currently under development within the EUROfusion project use as a breeder eutectic lithium-lead (PbLi). Since the inner walls of the blanket modules and the associated ancillary systems has to withstand severe corrosion attack, protective aluminum-based corrosion and tritium permeation barriers are being developed within the Breeding Blanket project. The goal of this activity is to evaluate properties of these protective coatings in conditions of a combined effect of hot PbLi and neutron irradiation from the LVR-15 reactor. The reduction effect of coatings on tritium permeation will be measured comparing the tritium permeation rate between coated and uncoated Eurofer samples. The paper presents the major results of the preliminary neutronics and thermal-hydraulics calculations leading to the proper design of the irradiation capsule which is also described in this paper.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

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)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2018

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

1873-7196

Svazek periodika

136

Číslo periodika v rámci svazku

SI

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

7

Strana od-do

797-802

Kód UT WoS článku

000452583700147

EID výsledku v databázi Scopus

2-s2.0-85046139731