Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Author:

Morita Koji1,Liu Wei1,Arima Tatsumi1,Arita Yuji2,Sato Isamu3,Matsuura Haruaki3,Sekio Yoshihiro4,Sagara Hiroshi5,Kawashima Masatoshi5

Affiliation:

1. Department of Applied Quantum Physics and Nuclear Engineering, Faculty of Engineering, Kyushu University , 744 Motooka, Nishi-ku, Fukuoka 819-0395, Japan

2. Research Institute of Nuclear Engineering, University of Fukui , 1-3-33 Kanawa-cho, Tsuruga-shi, Fukui 914-0055, Japan

3. Department of Nuclear Safety Engineering & Cooperative Major in Nuclear Energy, Tokyo City University , 1-28-1 Tamazutsumi, Setagaya-ku, Tokyo 158-8557, Japan

4. Oarai Research and Development Institute, Japan Atomic Energy Agency , 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan

5. Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology , 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550, Japan

Abstract

AbstractFollowing the Fukushima Nuclear Power Plant accident in 2011, it has become increasingly important for reactor safety designs to consider measures that can prevent the occurrence of severe accidents. This report proposes a novel subassembly-type passive reactor shutdown device that expands the diversity and robustness of core disruptive accident (CDA) prevention strategies for sodium-cooled fast reactors. The developed device contains pins with a fuel material that is in the solid state during normal operation but melts into a liquid when the temperature exceeds a certain value (i.e., during a potential accident). When an unprotected loss of flow (ULOF) or unprotected transient overpower (UTOP) accident occurs, the device can passively provide significant negative reactivity by rapidly transferring liquefied device fuel into the lower plenum region of the pins via gravitation alone. The reactors containing some of the proposed devices in place of original fuel subassemblies become subcritical before the driver fuels are damaged, even if ULOF or UTOP transient events occur. The present study evaluates candidate materials for device fuels (e.g., metallic alloy, chloride), optimal device pin structures for liquefied fuel relocation, and nuclear and thermal-hydraulic characteristics of the device-loaded core under accident conditions to demonstrate the engineering applicability of the proposed device. This report discusses preliminary results regarding the nuclear requirements for inducing negative reactivity to achieve reactor shutdown under the expected device conditions during an accident.

Funder

Ministry of Education, Culture, Sports, Science, and Technology

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference16 articles.

1. Ruggieri, J.-M., Ren, L., Glatz, J.-P., Ashurko, I., Hayafune, H., Kim, Y., and Hill, H., 2017, “ Sodium-Cooled Fast Reactor (SFR) System Safety Assessment, Generation IV International Forum,” accessed Feb. 11, 2023, https://www.gen-4.org/gif/upload/docs/application/pdf/2017-11/gif-sfr-safetyassessment-20170427_final.pdf

2. LMFBR Self-Actuated Shutdown Systems,1976

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