Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase

Research output: Contribution to journalArticle

Authors

  • Frederik Arbeiter
  • Ali Abou-Sena
  • Tim Böttcher
  • Yuming Chen
  • Bernhard Dolensky
  • Ulrich Fischer
  • Annette Heinzel
  • Volker Heinzel
  • Tobias Heupel
  • Christine Klein
  • Axel Klix
  • Keitaro Kondo
  • Joachim Konrad
  • Rainer Lindau
  • Anton Möslang
  • A. Muche
  • Harald Piecha
  • Rolf Rolli
  • Georg Schlindwein
  • Paul Schubert
  • Florian Schwab
  • Kevin Zinn

Institutes & Expert groups

  • IKET KIT INR - Karlsruhe Institute of Technology: Institut für Neutronenphysik und Reaktortechnik (INR) - Germany

Documents & links

DOI

Abstract

During the Engineering Validation and Engineering Design Activities (EVEDA) phase (2007-2014) of the International Fusion Materials Irradiation Facility (IFMIF), an advanced engineering design of the High Flux Test Module (HFTM) has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium) and insertion of Small Specimen Test Technique (SSTT) specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.

Details

Original languageEnglish
Pages (from-to)59-65
Number of pages7
JournalNuclear Materials and Energy
Volume9
DOIs
StatePublished - 1 Dec 2016

Keywords

  • IFMIF, EVEDA, HFTM, high flux test module, Neutron Irradiation, Irradiation Experiment, SSTT, Fusion, Helium Cooling, Engineering, Design Description, Validation, Prototype

ID: 5647864