Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors

Author:

Imaizumi Yuya,Aoyagi Mitsuhiro,Kamiyama Kenji,Matsuba Ken-ichi,Akaev AssanORCID,Mikisha Anatoly,Baklanov Viktor,Vurim Alexandr

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference29 articles.

1. Cao, X., Tobita, Y., 2000. Simulation of premixing experiment QUEOS by SIMMER-III, JNC TN9400 2000-100.

2. Elimination of recriticality potential for the self-consistent nuclear energy system;Endo;Prog. Nucl. Energy,2002

3. Hayafune, H., 1995. Summary of sodium boiling experiment and computer code development and future plan, PNC TN9410 95-238 (in Japanese).

4. Imaizumi, Y. et al., 2019. Development of evaluation method for in-place cooling of residual core materials in core disruptive accidents of SFRs, Proceedings of 27th International Conference on Nuclear Engineering (ICONE27), ICONE27-1768.

5. Japan Society of Mechanical Engineers, 1979. Hydraulic losses in pipes and ducts, Japan Society of Mechanical Engineers, 116 (in Japanese).

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