RBHT reflood heat transfer experiments data and analysis / prepared by L.E. Hochreiter [and others].

Format:

Book

Government document

Contributor:

Hochreiter, L. E.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Language:

English

Subjects (All):

Nuclear fuel rods--Experiments.

Nuclear fuel rods.

Heat-transfer media--Experiments.

Heat-transfer media.

Pressurized water reactors--Loss of coolant--Computer simulation.

Pressurized water reactors.

Nuclear power plants--Safety measures.

Nuclear power plants.

Physical Description:

1 online resource ([599] pages) : color illustrations

Other Title:

Rod Bundle Heat Transfer reflood heat transfer experiments data and analysis

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, [2012]

Notes:

"Date published: April 2012."

"NUREG/CR-6980."

Title from title screen (viewed on Dec. 27, 2012).

Includes bibliographical references.

Other Format:

Print version: RBHT reflood heat transfer experiments data and analysis

OCLC:

822976718