ML20072R397

Cobra/Trac - a THERMAL-HYDRAULICS Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems.Volume 2:COBRA/TRAC Numerical Solution Methods

ML20072R397
Person / Time
Issue date:	03/31/1983
From:	George T, Thurgood M Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
CON-FIN-B-2391 NUREG-CR-3046, NUREG-CR-3046-V02, NUREG-CR-3046-V2, PNL-4385, NUDOCS 8304050627
Download: ML20072R397 (64)