Cover Image

Critical heat flux experimentation in an annular test section. [PWR] [electronic resource]

Saved in:

Bibliographic Details
Online Access:	Online Access
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. Dept. of Energy, 1978.
Subjects:	Water Moderated Reactors. Water Cooled Reactors. Reactors. Structural Models. Critical Heat Flux. Departure Nucleate Boiling. Nucleate Boiling. Simulation. Boiling. Heat Transfer. Mockup. Test Facilities. Energy Transfer. Heat Flux. Transients. Blowdown. Pwr Type Reactors. Phase Transformations. Engineering. General Studies Of Nuclear Reactors. Specific Nuclear Reactors And Associated Plants.

Internet

Online Access

Online

Holdings details from Online
Call Number:	E 1.99:ornl/nureg/tm-180
E 1.99:ornl/nureg/tm-180	Available