In the last years considerable efforts have been made at the Institute for Transuranium Elements (ITU) in order to reestablish European knowledge and ability in safety testing of irradiated high temperature reactor (HTR) Fuel Elements. In the framework of the 6th European framework programme a cold finger apparatus (Ku¨FA) furnace, formerly installed at FZ-Ju¨lich (FzJ), has been installed in a hot cell at ITU [Freis 2008] in order to test fission product release under high temperature and non-oxidising conditions. Several analytical methods (e.g. Gamma-spectrometry, mass-spectrometry) have been applied in order to analyse different isotopes released during Ku¨FA tests. After the heating tests, examinations of the fuel elements were performed including scanning electron microscopy (SEM) and micro-hardness testing of coated particles. Individual coated particles were object of heating tests in a Knudsen cell with a coupled mass spectrometer measuring all released species. In order to cover more accident scenarios, a second furnace for oxidising-conditions (air- or water-ingress) was constructed and installed in a cold lab. Furthermore a disintegration apparatus, based on anodic oxidation, was constructed and fuel elements were dissolved obtaining thousands of individual coated particles for further examination. A fully automated irradiated microsphere gamma analyzer (IMGA) is under construction and will be used, in particular, to identify and sort out failed particles.
Skip Nav Destination
Sign In or Register for Account
Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4855-5
PROCEEDINGS PAPER
Post Irradiation Examination of HTR Fuel at ITU Karlruhe
D. Freis
,
D. Freis
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
P. D. Bottomley
,
P. D. Bottomley
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
J.-P. Hiernaut
,
J.-P. Hiernaut
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
J.-Y. Colle
,
J.-Y. Colle
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
J. Ejton
,
J. Ejton
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
W. de Weerd
W. de Weerd
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Search for other works by this author on:
D. Freis
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
P. D. Bottomley
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
J.-P. Hiernaut
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
J.-Y. Colle
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
J. Ejton
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
W. de Weerd
European Commission-JRC Institute for Transuranium Elements, Karlsruhe, Germany
Paper No:
HTR2008-58329, pp. 773-776; 4 pages
Published Online:
July 1, 2009
Citation
Freis, D, Bottomley, PD, Hiernaut, J, Colle, J, Ejton, J, & de Weerd, W. "Post Irradiation Examination of HTR Fuel at ITU Karlruhe." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 773-776. ASME. https://doi.org/10.1115/HTR2008-58329
Download citation file:
Sign In
4
Views
0
Citations
Related Proceedings Papers
Related Articles
Postirradiation Testing of High Temperature Reactor Spherical Fuel Elements Under Accident Conditions
J. Eng. Gas Turbines Power (April,2010)
Methodology of 63 Cu(n,2n) 62 Cu Reaction Rate Measurement
ASME J of Nuclear Rad Sci (April,2021)
Measurement of Selected Differential Cross Sections in 235 U Spectrum
ASME J of Nuclear Rad Sci (July,2019)
Related Chapters
Surface Analysis and Tools
Tribology of Mechanical Systems: A Guide to Present and Future Technologies
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Scope of Section I, Organization, and Service Limits
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition