Severe accident studies on the efficiency of mitigation devices in a SFR core with SIMMER code

Author:

Bachrata A.,Bertrand F.,Marie N.,Edeline A.,Kubota R.,Kamiyama K.,Kubo S.

Funder

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

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

Reference9 articles.

1. Code simulation of quenching of a high temperature debris bed: Model improvement and validation with experimental results;Bachrata;Int. Conf. Nuclear Eng., Proc., ICONE,2012

2. A three-dimensional neutronicics – Thermalhydraulics Unprotected Loss of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices;Bachrata;Nuclear Eng. Design,2019

3. Bachrata, A., 2015 et al., Unprotected loss of flow simulation on ASTRID CFV-V3 reactor core, Proc. Of the ICAPP 2015, Nice, France.

4. Status of severe accident studies at the end of the conceptual design of ASTRID: Feedback on mitigation features;Bertrand;Nucl. Eng. Design,2018

5. Status of the ASTRID core at the end of the preconceptual design phase;Chenaud;Nucl. Eng. Technol., Open Access,2013

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