Mitsubishi Heavy Industries (MHI) has developed the SPARKLE code, which is a PWR plant system transient analysis code that includes a three-dimensional (3D) neutronics module coupled with a thermal-hydraulics module. MHI has performed a study of the applicability of the SPARKLE code to the events which are associated with dynamic changes in power distribution, such as the rod ejection event or the steam line break event. In this paper, MHI has applied the SPARKLE code to the control rod drop event (drop of multiple rods), which features such a power distribution change. In addition, the neutron flux detection is dependent on the location of the dropped rods in this event, which can be dynamically calculated in the SPARKLE code. By applying the SPARKLE code to the control rod drop event, it was confirmed that the safety margin for this event is sufficiently larger than the margin calculated using the current safety analysis method, even if the appropriate conservative assumptions are made.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Safety Analysis of the Control Rod Drop Event Applying 3-D Neutronics/Thermal-Hydraulics Coupling Code SPARKLE
Yuta Maruyama,
Yuta Maruyama
Mitsubish Heavy Industries, Ltd., Kobe, Japan
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Satoshi Imura,
Satoshi Imura
Mitsubish Heavy Industries, Ltd., Kobe, Japan
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Junto Ogawa,
Junto Ogawa
Mitsubish Heavy Industries, Ltd., Kobe, Japan
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Shuhei Miyake
Shuhei Miyake
Mitsubish Heavy Industries, Ltd., Kobe, Japan
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Yuta Maruyama
Mitsubish Heavy Industries, Ltd., Kobe, Japan
Satoshi Imura
Mitsubish Heavy Industries, Ltd., Kobe, Japan
Junto Ogawa
Mitsubish Heavy Industries, Ltd., Kobe, Japan
Shuhei Miyake
Mitsubish Heavy Industries, Ltd., Kobe, Japan
Paper No:
ICONE17-75729, pp. 667-676; 10 pages
Published Online:
February 25, 2010
Citation
Maruyama, Y, Imura, S, Ogawa, J, & Miyake, S. "Safety Analysis of the Control Rod Drop Event Applying 3-D Neutronics/Thermal-Hydraulics Coupling Code SPARKLE." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 667-676. ASME. https://doi.org/10.1115/ICONE17-75729
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