Loss of feed flow, steam generator tube rupture, and steam line break thermohydraulic experiments
Subtitle: MB-2 steam generator transient response test program
By: prepared by Westinghouse Electric Corporation, Nuclear Technology Division ; principal investigators O.J. Mendler, K. Takeuchi, M.Y. Young ; contributors W.E. Barnhart, P.L. Hauck.
Contributors: Takeuchi, K.; Young, M. Y.; Barnhart, W. E.; Hauck, P. L.; Westinghouse Electric Corporation. Nuclear Technology Division.; U.S. Nuclear Regulatory Commission.
Publisher: U.S. Nuclear Regulatory Commission
Published: 1986
Place of publication: Washington, DC
Language: eng
Subjects: System failures (Engineering); Steam-boilers -- Failures.; Steam-boilers -- Hydrodynamics.; Tubes -- Fluid dynamics.
Notes: Distributed to depository libraries in microfiche.

"Date published: October 1986."

Bibliography: p. 10-1--10-2.

Technical.

Prepared for Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. B8252. NRC-04-82-020.

Electric Power Research Institute. EPRI project no. RP1845-08.

Westinghouse Electric Corporation.