Title of article
Graphite irradiation testing for HTR technology at the High Flux Reactor in Petten
Author/Authors
Vreeling، نويسنده , , J.A. and Wouters، نويسنده , , O. and Laan، نويسنده , , JG van der Bom، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
8
From page
68
To page
75
Abstract
In 2001 the Nuclear Research and Consultancy Group started a large graphite irradiation program for the development of High Temperature Reactor technology in the European framework. The irradiation experiments, containing present day available graphite grades, are performed at the High Flux Reactor in Petten. The grades are NBG-10, NBG-17, NBG-18, NBG-20, NBG-25, PCEA, PPEA, PCIB, LPEB, IG-110 and IG-430. In the fifth framework programme (2001–2004) and sixth framework programme (2005–2009) four irradiation experiments are foreseen, resulting in design curves at irradiation temperatures between 650 °C and 950 °C. The post-irradiation testing is focused on dimensional changes, dynamic Young’s modulus, coefficient of thermal expansion and coefficient of thermal conductivity. The irradiation programme and preliminary results from the first irradiation experiment at 750 °C to 8 dpa will be discussed in this paper.
Journal title
Journal of Nuclear Materials
Serial Year
2008
Journal title
Journal of Nuclear Materials
Record number
1364757
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