LOFT LOCA: WHAM6 model and code application

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Authors

V.T. Berta · Idaho Scientific (United States)

Abstract

This report documents the WHAM6 analysis of a loss-of-coolant accident (LOCA) pipe break at the reactor vessel. Data derived from this document is to be used to generate loads for the LOCA analysis of the reactor internals.

Topics & Keywords

Risk and Safety Analysis Nuclear Engineering Thermal-Hydraulics Nuclear Materials and Properties

Publication Details

DOI: 10.2172/6606934

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LOFT LOCA: WHAM6 model and code application

Authors

Abstract

Topics & Keywords

Publication Details