1979Nuclear TechnologyRequires access

TRAC Analysis of Loss-of-Fluid Test Non-Nuclear Test L1-4

J.J. Pyun, K.A. Williams

Open publisher page 2 citations

Abstract

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos Scientific Laboratory as an advanced “best-estimate” computer program for analyses of postulated accidents in light water reactors. As a part of the TRAC verification effort, a posttest analysis of loss-of-fluid test (LOFT) non-nuclear test L1-4 has been conducted. The results of this analysis show that TRAC accurately predicts the thermal-hydraulic response of the entire LOFT system, including the delayed effects from emergency core coolant injection into the cold leg.

About this research paper

What this paper is about

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos Scientific Laboratory as an advanced “best-estimate” computer program for analyses of postulated accidents in light water reactors. As a part of the TRAC verification effort, a posttest analysis of loss-of-fluid test (LOFT) non-nuclear test L1-4 has been conducted. The results of this analysis show that TRAC accurately predicts the thermal-hydraulic response of the entire LOFT system, including the delayed effects from emergency core coolant injection into the cold leg.

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OpenAlex reports 2 citations for this work. Citation counts describe recorded attention and do not establish research quality.

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Available abstract

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos Scientific Laboratory as an advanced “best-estimate” computer program for analyses of postulated accidents in light water reactors. As a part of the TRAC verification effort, a posttest analysis of loss-of-fluid test (LOFT) non-nuclear test L1-4 has been conducted. The results of this analysis show that TRAC accurately predicts the thermal-hydraulic response of the entire LOFT system, including the delayed effects from emergency core coolant injection into the cold leg.

Key concepts: TRAC, Nuclear engineering, Thermal hydraulics, Coolant, Transient (computer programming), Hydraulics, Environmental science, Computer science

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