MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part II: Analysis of containment thermal-hydraulics and ex-vessel phenomena-Reference-Cited by-同舟云学术

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MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part II: Analysis of containment thermal-hydraulics and ex-vessel phenomena

Published:2023-03 Issue: Volume:403 Page:112150
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Di Giuli M.,Yu S.,Swaidan A.M.,Barbion M.,Foucaud P.,Etienne C.,Dejardin P.

Funder

U.S. Nuclear Regulatory Commission

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

Reference28 articles.

1. On the heat and mass transport processes of horizontal melting or decomposing layer under a molten pool;Alsmeyer,1977

2. CPA module Containment Thermalhydraulics and Aerosol- and Fission Product Behaviour User Guidelines;Bestele,2000

3. Thermal hydraulic phenomena in corium pools for ex-vessel situations: the BALI experiment;Bonnet,2000

4. Modeling of heat transfer between core debris and concrete;Bradley,1988

5. CORCON-MOD3: An Integrated Computer Model for Analysis of Molten Core-Concrete Interactions. User’s Manual;Bradley,1993

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