Authors: WEGEN Detlef
Citation: 1st Annual Workshop Proceedings of the Collaborative Project “Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel” (7th EC FP CP FIRST-Nuclides) p. 17 - 20
Publisher: KIT Scientific Publishing
Publication Year: 2013
JRC N°: JRC83449
ISBN: 978-3-86644-980-0
URI: www.ksp.kit.edu
Type: Articles in periodicals and books
Abstract: Workpackage 2 (WP2) consists of two main components. In the first component "Experimental determination of fission gas release# the focus is on the quantification of fission gases and fission gas release in high burn-up (HBU) UO2 spent nuclear fuels (SNF). Fission gas sampled in the plenum of a fuel rod will be analysed as well as the grain boundary inventory and the cross sectional distribution of fission gases and volatile fission products. The second component "Rim and grain boundary diffusion# deals with investigations on oxygen diffusion in spent UO2-fuel. The examination diffusion effects will result in the quantification of water penetration into the grain structures and subsequent corrosion/diffusion phenomena. Furthermore, investigations on irradiated and unirradiated fuel kernels separated from high temperature reactor (HTR) fuel are planned which are complementary to those on light water reactor (LWR) fuel.
JRC Directorate:Nuclear Safety and Security

Files in This Item:
There are no files associated with this item.

Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.