Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 2 – Modelling of the fission products transport in the primary circuit and inside the containment-Reference-Cited by-同舟云学术

Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 2 – Modelling of the fission products transport in the primary circuit and inside the containment

Published:2021-10 Issue: Volume:382 Page:111377
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Shmelkov Yu.B.^ORCID,Zvonarev Yu.A.,Shutov N.V.,Petrov L.V.

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

Reference29 articles.

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3. P. Chatelard, N. Reinke. Overview of the integral code ASTEC V2.0. // Project reference ASTEC-V2/DOC/09-05.

4. LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT0;Clément;Nucl. Eng. Des.,2003

5. Aerosol Science;Davies,1966

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1. Analysis of the Influence of Aerosol Particle Size Distribution on the Behavior of Fission Products during Simulation of an Accident at an NPP with VVER;Thermal Engineering;2024-08

2. Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 3 – Modelling of the release of fission products from the melt;Nuclear Engineering and Design;2023-12