Development of models for the evaluation of temperatures in a HTGR core following a loss of forced circulation and simultaneous reactor trip

Development of models for the evaluation of temperatures in a HTGR core following a loss of forced circulation and simultaneous reactor trip [electronic resource]

Saved in:

Bibliographic Details
Online Access:	Online Access (via OSTI)
Corporate Author:	Oak Ridge National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1974.
Subjects:	Htgr Type Reactors > Loss Of Flow. Loss Of Flow > Temperature Distribution. After-Heat. Comparative Evaluations. Configuration. Data. Mathematical Models. Scram. Temperature Gradients. Transients. Vrain Reactor. N77900* > Reactors > Reactor Safety & Environmental Aspects. N77300 > Reactors > Power Reactors, Non-Breeding, Graphite Moderated.

Internet

Online Access (via OSTI)

Online

Holdings details from Online
Call Number:	E 1.99: cf--73-9-25
E 1.99: cf--73-9-25	Available