Assessment of core penetration of a PWR reactor vessel and particulate debris coolability in TLMBʹ, S2D, and ABG accidents
By: Ronald J. Lipinski [with] contributions by P.B. Bleiweis, J. Tills
Contributors: Bleiweis, P. B; Tills, J; Sandia National Laboratories; U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research
Publisher: U.S. Nuclear Regulatory Commission; Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; National Technical Information Service
Published: 1980
Place of publication: Washington, D.C; Springfield, Va
Language: eng
Number of pages: 59
Subjects: Pressurized water reactors -- Loss of coolant
Notes: "Sandia National Laboratories."

"Prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ... under Memorandum of Understanding DOE 40-550-75."

"NRC FIN no. A-1054."

"NUREG/CR-1518."

"SAND80-0701."

Includes bibliographical references