The elimination of severe power excursion during core disruptive accidents is a key issue for the enhanced safety of sodium-cooled fast reactors. In order to prevent the formation of a large-scale molten fuel pool within a reactor core, which is one of the factors leading to the severe power excursion, the Japan Atomic Energy Agency (JAEA) is considering the introduction of fuel assembly with inner duct structure (FAIDUS). In the current reference design for FAIDUS, the top end of the inner duct is open, whereas the bottom end is closed, and therefore it is expected that the molten fuel will be discharged from the reactor core towards the upper sodium plenum through the inner duct. The objective of the present study is to clarify the fundamental mechanism for upward fuel discharge through the inner duct structure, and thereby to confirm the effectiveness of FAIDUS. The possibility of upward discharge of a high-density melt driven by coolant vapor has been confirmed by the JAEA's experiment, in which molten Wood's metal simulating the molten fuel was injected into a coolant channel (equivalent inner diameter: 30 mm, total height: 2 m, fluid content: water) simulating the inner duct structure. In this paper, the mechanism of upward discharge of a high-density melt driven by coolant vapor pressure and/or flow in this experiment is discussed in terms of the application to reactor conditions. Through this discussion, the following mechanisms were clarified. (1) Coolant vapor pressure is built up within the coolant channel after the melt injection. The magnitude of the pressure buildup becomes larger with the increase of melt-enthalpy-injection rate, which is defined by the product of melt-mass-injection rate into the coolant channel and melt specific enthalpy. (2) Following the pressure buildup, the melt is discharged upward, being driven by the coolant vapor flow directing towards the top opening end of the coolant channel. The upward discharge mass rate becomes higher with the increase of the magnitude of the pressure buildup and, therefore, the melt-enthalpy-injection rate. The experimental knowledge obtained from the JAEA's experiment suggests that the coolant pressure buildup could act as one of the driving forces for the upward discharge of a high-density melt through the inner duct structure in FAIDUS under reactor conditions with higher melt-enthalpy-injection rate than the current simulant experimental condition.
Skip Nav Destination
Article navigation
March 2013
Research-Article
Mechanism of Upward Fuel Discharge During Core Disruptive Accidents in Sodium-Cooled Fast Reactors
Ken-ichi Matsuba,
Ken-ichi Matsuba
1
e-mail: matsuba.kennichi@jaea.go.jp
1Corresponding author.
Search for other works by this author on:
Mikio Isozaki,
Kenji Kamiyama,
Yoshiharu Tobita
Yoshiharu Tobita
e-mail: tobita.yoshiharu@jaea.go.jp
Advanced Nuclear System Research
and Development Directorate,
Oarai, Ibaraki, 311-1393,
Advanced Nuclear System Research
and Development Directorate,
Japan Atomic Energy Agency
,Oarai, Ibaraki, 311-1393,
Japan
Search for other works by this author on:
Ken-ichi Matsuba
e-mail: matsuba.kennichi@jaea.go.jp
Mikio Isozaki
e-mail: isozaki.mikio@jaea.go.jp
Kenji Kamiyama
e-mail: kamiyama.kenji@jaea.go.jp
Yoshiharu Tobita
e-mail: tobita.yoshiharu@jaea.go.jp
Advanced Nuclear System Research
and Development Directorate,
Oarai, Ibaraki, 311-1393,
Advanced Nuclear System Research
and Development Directorate,
Japan Atomic Energy Agency
,Oarai, Ibaraki, 311-1393,
Japan
1Corresponding author.
Contributed by the Nuclear Division of ASME for publication in the Journal of Engineering for Gas Turbines and Power. Manuscript received September 12, 2012; final manuscript received September 19, 2012; published online February 21, 2013. Editor: Dilip R. Ballal.
J. Eng. Gas Turbines Power. Mar 2013, 135(3): 032901 (9 pages)
Published Online: February 21, 2013
Article history
Received:
September 12, 2012
Revision Received:
September 19, 2012
Citation
Matsuba, K., Isozaki, M., Kamiyama, K., and Tobita, Y. (February 21, 2013). "Mechanism of Upward Fuel Discharge During Core Disruptive Accidents in Sodium-Cooled Fast Reactors." ASME. J. Eng. Gas Turbines Power. March 2013; 135(3): 032901. https://doi.org/10.1115/1.4007870
Download citation file:
Get Email Alerts
Cited By
An Adjustable Elastic Support Structure for Vibration Suppression of Rotating Machinery
J. Eng. Gas Turbines Power
Operation of a Compression Ignition Engine at Idling Load under Simulated Cold Weather Conditions
J. Eng. Gas Turbines Power
In-Cylinder Imaging and Emissions Measurements of Cold-Start Split Injection Strategies
J. Eng. Gas Turbines Power
Related Articles
Application of Fractional Scaling Analysis to Loss of Coolant Accidents, System Level Scaling for System Depressurization
J. Fluids Eng (August,2009)
Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study
J. Pressure Vessel Technol (February,2011)
Disjoining Pressure Effects in Ultra-Thin Liquid Films in Micropassages—Comparison of Thermodynamic Theory With Predictions of Molecular Dynamics Simulations
J. Heat Transfer (December,2006)
Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
ASME J of Nuclear Rad Sci (April,2019)
Related Proceedings Papers
Related Chapters
Dynamic Behavior of Pumping Systems
Pipeline Pumping and Compression Systems: A Practical Approach
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)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies