Preliminary Tritium Management Design Activities at ORNL

Thomas J. Harrison, David K. Felde, Randall J. Logsdon, Joanna McFarlane, A. L. Qualls

    Research output: Book/ReportCommissioned report

    Abstract

    Interest in salt-cooled and salt-fueled reactors has increased over the last decade (Forsberg et al. 2016). Several private companies and universities in the United States, as well as governments in other countries, are developing salt reactor designs and/or technology. Two primary issues for the development and deployment of many salt reactor concepts are (1) the prevention of tritium generation and (2) the management of tritium to prevent release to the environment. In 2016, the US Department of Energy (DOE) initiated a research project under the Advanced Reactor Technology Program to (1) experimentally assess the feasibility of proposed methods for tritium mitigation and (2) to perform an engineering demonstration of the most promising methods. This document describes results from the first year’s efforts to define, design, and build an experimental apparatus to test potential methods for tritium management. These efforts are focused on producing a final design document as the basis for the apparatus and its scheduled completion consistent with available budget and approvals for facility use.
    Original languageEnglish
    Place of PublicationUnited States
    DOIs
    StatePublished - 2016

    Keywords

    • 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
    • 42 ENGINEERING
    • TRITIUM
    • DESIGN
    • MANAGEMENT
    • FEASIBILITY STUDIES
    • MITIGATION
    • MOLTEN SALT COOLED REACTORS
    • MOLTEN SALT FUELED REACTORS
    • TRITIUM RECOVERY

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