ML20198B467

COBRA-NC:A THERMAL-HYDRAULIC Code for Transient Analysis of Nuclear Reactor Components.Volume 2:COBRA-NC Numerical Solution Methods

ML20198B467
Person / Time
Issue date:	04/30/1986
From:	George T, Thurgood M, Wheeler C Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
CON-FIN-B-2466 NUREG-CR-3262, NUREG-CR-3262-V02, NUREG-CR-3262-V2, PNL-5515, NUDOCS 8605220014
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