Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor
Subtitle: case study
By: prepared by W.R. Cramond, D.M. Ericson, Jr., G.A. Sanders.
Contributors: Ericson, David M.; Sanders, Gary A.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor and Plant Systems.; Sandia National Laboratories.
Publisher: Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1987
Place of publication: Washington, DC
Language: eng
Subjects: Pressurized water reactors -- Critical heat flux.; Pressurized water reactors -- Emergency core cooling systems.; Nuclear power plants -- Florida -- Risk assessment.
Notes: "Sandia National Laboratories."

Distributed to depository libraries in microfiche.

"Date published: August 1987."

Includes bibliographies.

Technical.

Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission. A1309.