AGC 2 Irradiated Material Properties Analysis [electronic resource]

Advanced Graphite Creep;High Temperature Reactor;Post Irradiation Examination.

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Bibliographic Details
Online Access:	Online Access (via OSTI)
Corporate Author:	Idaho National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C. : Oak Ridge, Tenn. : United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 2017.
Subjects:	Graphite. Reactor Design. Htr Reactor. Thermodynamic Properties. Htgr Type Reactors. Irradiation. Reactor Technology. Materials Science.

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Online Access (via OSTI)

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Call Number:	E 1.99:inl/ext--17-41165
E 1.99:inl/ext--17-41165	Available