COBRA-NC : a thermal-hydraulic code for transient analysis of nuclear reactor components.

Bibliographic Details
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation U.S. Nuclear Regulatory Commission. Division of Reactor System Safety Pacific Northwest Laboratory
Other Authors:	Wheeler, C. L.
Language:	English
Published:	Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986-
Subjects:	Nuclear reactors > Thermodynamics > Computer programs. Nuclear reactors > Containment > Computer programs. Two-phase flow > Computer programs.
Physical Description:	volumes : illustrations ; 28 cm
Format:	Government Document Microfilm Book

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