Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions

作者:Gonzalez Robles E; Metz V; Wegen D H; Herm M; Papaioannou D; Bohnert E; Gretter R; Mueller N; Nasyrow R; de Weerd W; Wiss T; Kienzler B
来源:Journal of Nuclear Materials, 2016, 479: 67-75.
DOI:10.1016/j.jnucmat.2016.06.035

摘要

Abstract(#br)During reactor operation the fission gases Kr and Xe are formed within the UO 2 matrix of nuclear fuel. Their quantification is important to evaluate their impact on critical parameters regarding the fuel behaviour during irradiation and (long-term) interim storage, such as internal pre...

  • 出版日期2016-10