|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Determination of the hydrogen heat of transport in Zircaloy-4
||Soyoung Kang, Pei-Hsun Huang, Victor Petrov, Annalisa Manera, Taehwan Ahn, Arthur Motta
|On-Site Speaker (Planned)
The corrosion of zirconium alloys during normal operation of nuclear fuel cladding produces hydrogen gas, a fraction of which enters the cladding. Once the hydrogen in solid solution exceeds the terminal solid solubility hydrides can precipitate. Hydrogen in the cladding can redistribute driven by concentration (Fick’s Law) and temperature gradients (Soret Effect), causing the distribution to be inhomogeneous. Therefore, understanding hydrogen migration is important. Migration driven by the Soret Effect is governed by the heat of transport value (Q*) which can be used in the fuel performance code BISON to predict hydrogen behavior in cladding. A series of controlled hydrogen migration tests were conducted to determine Q*. Hydrogen charged Zircaloy-4 sheets were annealed under a linear temperature gradient and using a range of temperatures until a steady state hydrogen distribution was reached. These are discussed and compared with existing literature.
||Nuclear Materials, Other,