MELT-I [electronic resource] : A SIMPLIFIED MELTDOWN CODE FOR FAST REACTOR SAFETY ANALYSIS.

Reactors, Fast/core Behavior In Liquid Sodium-cooled, Melt-1 Heat Transfer-- Neutronics Computer Program For Major Excursion Effects On; Reactors, Liquid Metal-cooled/core Behavior In Fast, Melt-1 Heat Transfer--neutronics Computer Program For Major Excursion Effects On; Computer Programs/ Melt-1, H...

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Bibliographic Details

Online Access:	Online Access
Corporate Authors:	Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1968.
Subjects:	Liquid Metal Coolant. Digital Systems. Excursions. Fortran. Univac 1108. Reactors. Computers. Reactor Safety. Fast Neutrons. Heat Transfer. Fast Reactors. Univac. Reactivity. Programming.