The accomplishments of lithium target and test facility validation activities in the IFMIF/EVEDA phase

Research output: Contribution to journalArticle

Authors

  • Frederik Arbeiter
  • Nadine Baluc
  • Paolo Favuzza
  • Friedrich Gröschel
  • Roland Heidinger
  • Angel Ibarra
  • Vincent Massaut
  • Franceso Saverio Nitti
  • Gioacchino Miccichè
  • Shigeru O’hira
  • David Rapisarda
  • Masayoshi Sugimoto
  • Eiichi Wakai
  • Takehiko Yokomine

Institutes & Expert groups

  • IKET KIT INR - Karlsruhe Institute of Technology: Institut für Neutronenphysik und Reaktortechnik (INR) - Germany
  • CRPP - Center for Reasearch in Plasma Physics - EPFL - Swiss Federal Institute of Technology Lausanne
  • ENEA - Italian National Agency for New Technologies
  • Max Planck Institute - CIPS - Centre for Interdisciplinary Plasma Science
  • CIEMAT - Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas - Spain
  • QST - National Institutes for Quantum and Radiological Science and Technology
  • JAEA - Japan Atomic Energy Agency
  • Kyoto University

Documents & links

DOI

Abstract

As part of the engineering validation and engineering design activities (EVEDA) phase for the international fusion materials irradiation facility IFMIF, major elements of a lithium target facility and the test facility were designed, prototyped and validated. For the lithium target facility, the EVEDA lithium test loop was built at JAEA and used to test the stability (waves and long term) of the lithium flow in the target, work out the startup procedures, and test lithium purification and analysis. It was confirmed by experiments in the Lifus 6 plant
at ENEA that lithium corrosion on ferritic martensitic steels is acceptably low. Furthermore, complex remote handling procedures for the remote maintenance of the target in the test cell environment were successfully practiced. For the test facility, two variants of a high flux test module were prototyped and tested in helium loops, demonstrating their good capabilities of maintaining the material specimens at the desired temperature with a low temperature spread.
Irradiation tests were performed for heated specimen capsules and irradiation instrumentation in the BR2 reactor at SCK-CEN. The small specimen test technique, essential for obtaining material test results with limited irradiation volume, was advanced by evaluating specimen shape and test technique influences.

Details

Original languageEnglish
Article number 015001
Number of pages6
JournalNucl. Fusion
Volume58
Issue number(2018) 015001
DOIs
StatePublished - 10 Nov 2017

Keywords

  • litium target, IFMIF, EVEDA, Fusion, validation activities

ID: 3239659