Studies on the suppression of the reactivity of sodium itself have been performed on the basis of the concept of suspended nanoparticles in liquid sodium (sodium nanofluid). According to the theoretical and experimental results of studies for sodium nanofluid, velocity and heat of sodium nanofluid reaction with water (sodium nanofluid/water reaction) are lower than those of the pure sodium/water reaction. The analytical model for the peak temperature of a sodium nanofluid/water reaction jet has been developed by the authors in consideration of these suppression effects. In this paper, the prediction method for mitigation effects on damage of adjacent tubes in steam generator tube rupture (SGTR) accidents is developed by applying this analytical model for the peak temperature of the reaction jet. On the assumption that the sodium nanofluid is used for the secondary coolant of sodium-cooled fast reactor (SFR), mitigation effects under the design basis accident (DBA) condition and the design extension condition (DEC) of SGTR are estimated by using this method. The results indicate a clear possibility to reduce the number of damaged tubes and to suppress the pressure generated in SGTR accidents by using sodium nanofluid as the secondary coolant.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5143-2
PROCEEDINGS PAPER
Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR
Kenta Ichikawa,
Kenta Ichikawa
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Search for other works by this author on:
Hironori Kanda,
Hironori Kanda
Japan Atomic Energy Agency, Narita, Japan
Search for other works by this author on:
Naoki Yoshioka,
Naoki Yoshioka
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Search for other works by this author on:
Kuniaki Ara,
Kuniaki Ara
Japan Atomic Energy Agency, Narita, Japan
Search for other works by this author on:
Jun-ichi Saito,
Jun-ichi Saito
Japan Atomic Energy Agency, Narita, Japan
Search for other works by this author on:
Keiichi Nagai
Keiichi Nagai
Japan Atomic Energy Agency, Narita, Japan
Search for other works by this author on:
Kenta Ichikawa
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Hironori Kanda
Japan Atomic Energy Agency, Narita, Japan
Naoki Yoshioka
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Kuniaki Ara
Japan Atomic Energy Agency, Narita, Japan
Jun-ichi Saito
Japan Atomic Energy Agency, Narita, Japan
Keiichi Nagai
Japan Atomic Energy Agency, Narita, Japan
Paper No:
ICONE26-81309, V001T13A006; 6 pages
Published Online:
October 24, 2018
Citation
Ichikawa, K, Kanda, H, Yoshioka, N, Ara, K, Saito, J, & Nagai, K. "Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR." Proceedings of the 2018 26th International Conference on Nuclear Engineering. London, England. July 22–26, 2018. V001T13A006. ASME. https://doi.org/10.1115/ICONE26-81309
Download citation file:
15
Views
Related Proceedings Papers
Related Articles
Selection of an Ideal Coolant to Ward Off the Thermal Runaway of a Pouch Type Li-Ion Battery Module
J. Electrochem. En. Conv. Stor (May,2021)
Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
J. Pressure Vessel Technol (April,2012)
Critical Heat Flux (CHF) of Subcooled Flow Boiling of Alumina Nanofluids in a Horizontal Microchannel
J. Heat Transfer (October,2010)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies