RELAP4/MOD5 [electronic resource] : a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation. [PWR and BWR].

Published: Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1976.
Physical Description: Pages: 445 : digital, PDF file
Additional Creators: United States. Department of Energy. Office of Scientific and Technical Information

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Summary

This portion of the RELAP4/MOD5 User's Manual presents the details of setting up and entering the reactor model to be evaluated. The input card format and arrangement is presented in depth, including not only cards for data but also those for editing and restarting. Problem initalization including pressure distribution and energy balance is discussed. A section entitled ''User Guidelines'' is included to provide modeling recommendations, analysis and verification techniques, and computational difficulty resolution. The section is concluded with a discussion of the computer output form and format.

Report Numbers

E 1.99:ancr-nureg-1335(vol.2)
ancr-nureg-1335(vol.2)

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Note

Published through SciTech Connect.
09/01/1976.
"ancr-nureg-1335(vol.2)"
Idaho National Engineering Lab., Idaho Falls (USA)

Funding Information

E(10-1)-1375

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