Title of article
Thermal treatment of neutron-irradiated nuclear graphite
Author/Authors
Vulpius، نويسنده , , Dirk and Baginski، نويسنده , , Kathrin and Kraus، نويسنده , , Benjamin and Thomauske، نويسنده , , Bruno، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2013
Pages
16
From page
294
To page
309
Abstract
The properties of graphite samples from the thermal column of a material testing reactor and from the internals of two different nuclear power reactors were investigated regarding the thermal release of tritium and radiocarbon. These reactor types have been selected due to the different conditions under which graphite has been irradiated with neutrons during the operating time of these reactors. Based on the findings, options for thermal treatment of irradiated graphite are discussed in order to facilitate its final disposal.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2013
Journal title
Nuclear Engineering and Design Eslah
Record number
1593667
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