Recent accomplishments of the fusion safety program at the Idaho National Laboratory

Brad J. Merrill, Lee C. Cadwallader, Masashi Shimada, Paul W. Humrickhouse, Chase N. Taylor, Dean A. Stewart, Robert J. Pawelko

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

The Idaho National Laboratory (INL) Fusion Safety Program (FSP) is the Office of Fusion Energy Sciences’ (FES) lead laboratory for Magnetic Fusion Energy (MFE) Safety. Our mission is to assist the US and international fusion communities in developing the inherent safety and environmental potential of fusion power by: 1) Developing fusion licensing data and analysis tools, 2) Participating in national and international collaborations and design studies, and 3) Assisting the US and international fusion community in licensing activities and guidance in operational safety. To achieve our mission, the FSP maintains core competencies in the several areas, two of which are: fusion safety code development and tritium retention and permeation in fusion plasma facing component (PFC) and blanket materials. This article details recent accomplishments of our program in these areas and future directions for fusion safety research and development at INL.

Original languageEnglish
Pages (from-to)1106-1111
Number of pages6
JournalFusion Engineering and Design
Volume136
DOIs
StatePublished - Nov 2018
Externally publishedYes

Funding

This material is based upon work supported by the U.S. Department of Energy Office of Science , Office of Fusion Energy Sciences , under the DOE Idaho Operations Office contract number DE-AC07-05ID14517. This material is based upon work supported by the U.S. Department of Energy Office of Science, Office of Fusion Energy Sciences, under the DOE Idaho Operations Office contract number DE-AC07-05ID14517.

FundersFunder number
U.S. Department of Energy Office of Science
U.S. Department of EnergyDE-AC07-05ID14517
Fusion Energy Sciences

    Keywords

    • Fusion safety
    • MELCOR
    • STAR facility
    • TMAP
    • Tritium transport

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