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Licensed Unlicensed Requires Authentication Published by De Gruyter December 25, 2019

Investigation of the 3D hydrogen distribution in zirconium alloys by means of neutron tomography

Paper presented at the Symposium “Tomographic and Radiographic Imaging with Synchrotron X-rays and Neutrons” of the MSE 2018, 26–28 September 2018, Darmstadt, Germany

  • M. Grosse , B. Schillinger , P. Trtik , N. Kardjilov and M. Steinbrück


The fuel rod claddings in nuclear light water reactors are made of zirconium alloys. Corrosion of these alloys during operation and in particular high temperature oxidation during nuclear accidents results in the production of free hydrogen. The cladding can absorb this hydrogen. It affects the mechanical properties of the cladding material. Hydrogen embrittlement of these materials provides the risk of brittle fracture of the cladding by thermo-shock during emergency cooling. At KIT the behaviour of cladding materials under different hypothetical nuclear accident scenarios was investigated. One focus was on hydrogen absorption and distribution/re-distribution in the alloys. The hydrogen distribution was determined mainly by neutron tomography. Examples for the determination of the 3D hydrogen distribution in cladding tubes after loss of coolant accident simulation tests are given and discussed.

Correspondence address, Mirco Grosse, IAM-AWP, Karlsruhe Institute of Technology, P.O. Box 3640, D-76021 Karlsruhe, Germany, Tel.: +49 721 608 23884, Fax: +49 721 608 24567, E-mail:


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Received: 2018-11-05
Accepted: 2019-11-15
Published Online: 2019-12-25
Published in Print: 2020-01-09

© 2020, Carl Hanser Verlag, München

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