Abstract
We performed a hydrogen combustion analysis in the Advanced Power Reactor 1400 MWe (APR1400) containment during a severe accident initiated by a small break loss of coolant accident (SBLOCA) which occurred at a lower part of the cold leg using a multi-dimensional hydrogen analysis system (MHAS) to confirm the integrity of the APR1400 containment. The MHAS was developed by combining MAAP, GASFLOW, and COM3D to simulate hydrogen release, distribution and combustion in the containment of a nuclear power plant during the severe accidents in the containment of a nuclear power reactor. The calculated peak pressure due to the flame acceleration by the COM3D, using the GASFLOW results as an initial condition of the hydrogen distribution, was approximately 555 kPa, which is lower than the fracture pressure 1223 kPa of the APR1400 containment. To induce a higher peak pressure resulted from a strong flame acceleration in the containment, we intentionally assumed several things in developing an accident scenario of the SBLOCA. Therefore, we may judge that the integrity of the APR1400 containment can be maintained even though the hydrogen combustion occurs during the severe accident initiated by the SBLOCA.
Highlights
A hydrogen explosion accident, which was started from a station blackout (SBO)induced by the tsunami, occurred at the nuclear power plants (NPP) with a boiling water reactor in Fukushima in 2011 and released a significant amount of radioactive materials into the environment through a broken part of a reactor building containment [1]
We performed the hydrogen combustion analysis in the Advanced Power Reactor 1400 MWe (APR1400) containment during the severe accident initiated by the small break loss of coolant accident (SBLOCA) which occurred at the lower part of the cold leg using the multi-dimensional hydrogen analysis system (MHAS), which consists of MAAP, GASFLOW, and COM3D, to confirm the integrity of the APR1400 containment
Through the COM3D calculation for the flame acceleration, we found that the calculated peak pressure of approximately 555 kPa was lower than the fracture pressure 1223 kPa of the APR1400
Summary
Induced by the tsunami, occurred at the nuclear power plants (NPP) with a boiling water reactor in Fukushima in 2011 and released a significant amount of radioactive materials into the environment through a broken part of a reactor building containment [1]. A 100% metal-water reaction in the reactor pressure vessel (RPV) was assumed in developing the severe accident scenario to induce a higher hydrogen concentration in the containment according to the safety review guidelines [20]. This calculation result may have resulted from the design features of the APR1400 containment which are a large air free volumes of approximately 88,631 m3 in the cylindrical dome geometry with diameter 45.72 m and height 69.69 m and an opening structure of the steam generator (SG) compartments where the hydrogen was discharged upward to the upper region by the safety depressurization system [3,19]. The cylindrical geometry of the grid model is changed to the cartesian geometry, and its cell size is changed to a smaller length to accurately analyze the hydrogen flame acceleration and pressure wave propagation along the important small structures in the containment
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