Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data-Reference-Cited by-同舟云学术

Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data

Published:2019-10 Issue: Volume:352 Page:110152
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Narcisi Vincenzo^ORCID,Giannetti Fabio^ORCID,Caruso Gianfranco^ORCID

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference39 articles.

1. Testing and qualification of CIRCE Venturi-nozzle flow meter for large scale experiments;Agostini,2005

2. A validation of RELAP on predicting nuclear power plant phenomena;Ahn,2018

3. Testing and qualification of CIRCE instrumentation based on bubble tubes;Ambrosini;Jou. Nuc. Mat.,2004

4. STH-CFD codes coupled calculations applied to HLM loop and pool systems;Angelucci;Sci. Tech. Nucl. Ins.,2017

5. Bayless, P.D., et al., 2015. RELAP5-3D Code Manual Vol. III: Developmental Assessment. INL/MIS-15-36723 Volume I, Revision 4.3.

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