Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750°C

Author:

Marsden Barry J.,Hall Graham N.,Wouters Onne,Vreeling J.A.,van der Laan J.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. The Story of Gilsonite;Kretchman,1957

2. S. Mrozowski, Mechanical strength, thermal expansion and structure of cokes and carbons, in: First Biennial Conference on Carbon, University of Buffalo, Buffalo, 1953.

3. The dimensional changes of highly oriented pyrolytic graphite irradiated with fast neutrons at 430°C and 600°C;Brocklehurst;Carbon,1993

4. E.D. Eason, G. Hall, B.J. Marsden, Development of a model of dimensional change in AGR graphites irradiated in inert environments, in: Ageing Management of Graphite Reactor Cores Conference, 28–30th November, 2005.

5. The development of a stress analysis code for nuclear graphite components in gas-cooled reactors

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