Interfacial heat transfer with non-condensable gas in ASTEC V2.2: Application to severe accidents study during PWR cold shutdown states

Author:

Zambaux J.A.,Laborde L.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

Reference17 articles.

1. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs, VVERs;Aksan;Nucl. Eng. Des.,2019

2. Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation;Bandini;Prog. Nucl. Energy,2010

3. L. Chailan, A. Bentaïb, P. Chatelard, “Overview of ASTEC code and models for Evaluation of Severe Accidents in Water Cooled Reactors”,Proceedings of IAEA Technical Meeting on Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors, Vienna (Austria), October 9-12, 2017.

4. P. Coste and D. Bestion, “A simple modelling of mass diffusion effects on condensation with noncondensable gases for the Cathare code”, NURETH 7, Saratoga Springs, NY (United States), September 10-15th 1995.

5. Loss of residual mid-loop operation: BETHSY experiments;Dumont;Nucl. Eng. Des.,1994

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