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

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

Published:2022-02 Issue: Volume:387 Page:111248
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Di Giuli M.,Malicki M.,Dejardin P.,Corda V.^ORCID,Swaidan A.M.

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

Reference23 articles.

1. Andrews, N., Faucett, C., Belon, S., Bouillet C., Bonneville, H., 2019. MELCOR ASTEC Crosswalk of the Accident of Fukushima Daiichi Unit 1: Phase 1 Analysis. NUREG/IA-0510.

2. Bandini, G., et al., "Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding." NEA/CSNI/R(2009)3, 2009.

3. ASTEC validation on TMI-2 and LOFT LP-FP-2;Bandini;Nucl. Energy Design,2013

4. Chailan, L., Bosland L., Carénini, L., Chambarel J., Cousin F., Chatelard P., Drai P., Kioseyian, G, Phoudiah S., Topin V. Overview of ASTEC integral code status and perspectives. In: 9th European Review Meeting on Severe Accident Research (ERMSAR 2019) March 18–20, Prague, Czech Republic.

5. Main modelling features of the ASTEC V2. 1 major version;Chatelard;Ann. Nucl. Energy,2016

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