Compatibility of structural materials for fusion reactors with candidate blankets and coolants.

F. Casteels, Ja De Keyser, M. Soenen, H. Tas, J. Dresselaers

    Research outputpeer-review

    Abstract

    Corrosion and deposition rates and mechanisms have been determined of austenitic (AISI 316, AISI 304, AISI 316L, Nitronic 33, Nitronic 40, Carpenter 18/18 plus) and ferritic (WN 1. 4922, EM12, DT02) steels, with the light alloy Ti 6Al4V and refractory alloys (Nb, V20%Ti, TZM) exposed in the hot and cold section of a pumped loop system. The reactor loop system was operated for total exposure times up to 7400 hours with pure lithium.

    Original languageEnglish
    Title of host publicationTransactions of the International Conference on Structural Mechanics in Reactor Technology
    PublisherIASMiRT - International Assn for Structural Mechanics in Reactor Technology
    Number of pages2
    ISBN (Print)0444867023
    StatePublished - 1983
    Event1983 - SMiRT 7 - Chicago
    Duration: 22 Aug 198326 Mar 2019

    Publication series

    NameTransactions of the International Conference on Structural Mechanics in Reactor Technology
    ISSN (Print)0167-563X

    Conference

    Conference1983 - SMiRT 7
    Country/TerritoryUnited States
    CityChicago
    Period1983-08-222019-03-26

    ASJC Scopus subject areas

    • General Engineering

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