Component Category: --Fuel matrices
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Development work for the moderator of the ITR-fuel Entwicklungsarbeiten zum ITR-Brennstoff-Moderator
Duenner, P.;Becker, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--73.42 - German - 1973
Abstract: In the frame of the ITR-project (Incore-Thermionic-Reactor) fuel-moderator-materials had been investigated, which are also of interest for the KNK-project and which are therefore documented in this report. Partial pressure measurements on the systems Zr-H, Zr U-H, Y-H and YH-H revealed the premise for the elaboration of a hydration technique. On the basis of the functional relation between partial H2-pressure, temperature and H2-content of the hydride, an optimum hydration kinetic for the production of flawless and well defined hydrated Zirconium hydride/Uranium pellets and of Zirconium hydride and Yttrium hydride moderator bodies was developed. Alternatively to the ZrHx-U-technology a powder- metallurgical procedure for the production of a Y-U sinter-alloy as base material was tested. In an irradiation experiment in the DIDO reactor (in Juelich) the burnup behavior of Zirconium hydride-Uranium and Yttrium hydride-Uranium under ITR-similar conditions has been tested. With a U235-burnup of 6.75 % and an irradiation temperature of 490 deg C a fission gas release rate of 0.1 % was observed. The ZrHx-pellets remained mechanically intact, whereas the YHx-pellets crumbled during the post-examinations. The ZrHx-U showed a maximum density reduction of 4.2 %
Key words: burnup;dido reactor;fission product release;fuel pellets;hydration;irradiation;knk-2 reactor;materials testing;thermionic reactors;uranium;yttrium hydrides;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
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