A method for the analysis of hydrogen and steam releases to containment during degraded core cooling accidents
By: prepared by P. Cybulskis ; prepared for Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Contributors: U.S. Nuclear Regulatory Commission. Division of Risk Analysis.; Battelle Memorial Institute. Columbus Laboratories.
Publisher: The Commission; Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; National Technical Information Service
Published: 1982
Place of publication: Washington, D.C; Springfield, Va
Language: eng
Subjects: Hydrogen -- Analysis.; Pressurized water reactors -- Loss of coolant.; Nuclear reactors -- Containment.
Notes: "Battelle Columbus Laboratories."

"Date published: February 1982."

"NRC FIN A4067."

"NUREG/CR-2540."

"BMI-2090."

Includes bibliographical references.