2D and 3D numerical investigations of sodium boiling in sodium cooled fast reactor with MOX fuel and low sodium void reactivity effect during unprotected loss of flow accidents-Reference-Cited by-同舟云学术

2D and 3D numerical investigations of sodium boiling in sodium cooled fast reactor with MOX fuel and low sodium void reactivity effect during unprotected loss of flow accidents

Published:2021-02 Issue: Volume:372 Page:110961
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Raskach Kirill,Volkov Andrey,Lemasson David^ORCID,Solomonova Nataliya,Moryakov Aleksey,Yakunin Andrey

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. Anderhuber, M., Gerschenfeld, A., Gorsse, Y., Alpy, N., Latge, C., Perez-Manes, J., Kuzina, Yu., Sorokin, A., Berensky, I., Volkov, A., Chernukhina, Yu., Raskach, K. 2019. Prospects for a CEA and ROSATOM/IPPE collaborative program on na boiling for GENIV SFRs safety: Rationale and thermal-hydraulic preparatory work. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). Portland, OR, August 18–23.

2. Coremelt-2D code for analysis of severe accidents in a sodium fast reactor;Ashurko,2013

3. Comparison of the behaviour of two core designs for ASTRID in case of severe accidents;Bertrand;Nucl. Eng. Des.,2016

4. Status of the ASTRID Core at the End of the Pre-Conceptuel Design Phase 1;Chenaud;Nucl. Eng. Technol.,2013

5. Physical tool for unprotected loss of flow transient simulations in a sodium fast reactor;Droin;Nucl. Eng. Des.,2017

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