Session: CS-15-01 Mechanical Properties of Nuclear Graphite and Their Implementation in Codes and Standards (Joint with MF-29) – 1

Paper Number: 105928

105928 - Creep and Mechanical Properties Testing for Neutron Irradiated Graphite 

Irradiation induced creep and mechanical properties data of neutron irradiated graphite is required to ultimately provide for the safe and economical operation of graphite moderated reactors. This data is acquired through irradiation tests such as performed at the High Flux Reactor, which is operated by NRG in Petten, the Netherlands. Experimental campaigns are performed in support of both long term operation (LTO) of Advanced Gas Cooled Reactors and the qualification of graphite for advanced reactors (High Temperature Reactors and Molten Salt Reactors).

This paper presents the technical aspects for consideration in 1) the design of irradiation experiments and 2) testing of neutron irradiated graphite specimens. Key aspects for irradiation testing are the control of relevant irradiation parameters, being: temperature, dose and stress for graphite irradiation creep experiments. In addition, the environment of the graphite specimens (gas or molten salt) during irradiation needs to be designed and operated such that representative irradiation data is obtained. Considerations for specimen design, e.g. geometry and size, are discussed in relation to both the loading of irradiation experiments and measurement of neutron irradiated graphite properties. The different design and operational aspects that are discussed in this paper will be related to recent irradiation campaigns in the High Flux Reactor that are performed support of LTO and the qualification of nuclear graphite.

Presenting Author: Tjark van Staveren NRG

Presenting Author Biography: Tjark van Staveren has a background in materials science and is active on (graphite) irradiation projects at NRG for more than 10 years. He has worked on projects in support of life time extension of existing NPPs and materials qualification for GenIV reactors.

Authors:

Tjark van Staveren NRG