TRAC independent assessment for PWR analysis [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Los Alamos National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Los Alamos, N.M. : Oak Ridge, Tenn. : Los Alamos National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1983.
Subjects:	Loft Reactor. Computer Calculations. Loss Of Coolant. Pwr Type Reactors. Reactor Safety Experiments. Computer Codes. T Codes. Accidents. Reactor Accidents. Reactors. Research And Test Reactors. Tank Type Reactors. Test Reactors. Water Cooled Reactors. Water Moderated Reactors. General Studies Of Nuclear Reactors. Specific Nuclear Reactors And Associated Plants.

Description
Abstract:	LANL is developing the Transient Reactor Analysis Code (TRAC) for application to PWRs. Goal was to analyze large-break loss-of-coolant accidents (LOCAs), and the TRAC-P1A and TRAC-PD2 codes primarily addressed the large-break LOCA. The TRAC-PF1 code contained modifications which enhanced the computational speed of the code and improved its application to small-break LOCAs. The TRAC-PF1/MOD1 code added improved steam-generator modeling, a turbine component, and a control system together with modified constitutive relations to model the balance of plant on the secondary side and to extend the applications to non-LOCA transients. During the past year we assessed TRAC-PD2, TRAC-PF1, and TRAC-PF1/MOD1, using LOFT and Semiscale experiments.
Item Description:	Published through SciTech Connect. 01/01/1983. "la-ur-83-3127" " conf-8310143-20" "DE84001744" 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983. Knight, T.D.
Physical Description:	Pages: 14 : digital, PDF file.

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