Analysis of the configurations and heat transfer of corium pool in RPV lower plenum

Liu, Lili; Yu, Hongxing; Deng, Jian; Chen, Liang; Deng, Chunrui; Xiang, Qingan; Wu, Lingjun

doi:10.1016/j.anucene.2018.10.002

Cited by 3 publications

(2 citation statements)

References 11 publications

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“…In general, the results of this study indicate that the MPS method has the capacity to analyze the penetration behavior of melt in the instrument tube of the reactor vessel [5].…”

Section: Theoretical Backgroundmentioning

confidence: 72%

“…If the heat flux generated in a part is greater than the critical heat flux that can be compensated by the reactor vessel, then the reactor vessel will experience a decrease in integrity resulting in reactor vessel failure. In addition, at certain compositions, a corium pool can be formed with the bottom layer in the form of heavy metals which can increase the thermal load in the lower plenum [5]. Furthermore, it is likely that debris will form as a result of the corium freezing on contact with water.…”

Section: Parameter III Survey: Lower Plenum Variation 4000k and Coriummentioning

confidence: 99%

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Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

Irfan¹,

Humolungo²,

Mustari³

et al. 2023

CERiMRE

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System failure in nuclear reactors can cause degradation of a reactor core, allowing melting and relocation of the corium to the lower plenum in the nuclear reactor system. In this study, a severe accident simulation was carried out using the Moving Particle Semi-Implicit (MPS) method. In this method, we model the relocation of molten corium on the reactor core (support plate) to the lower plenum for several conditions with variations: corium material, lower plenum conditions, temperature, viscosity, and density. Those treatments were carried out in order to be able to compare and analyze the characteristics of the corium melt by reviewing the velocity profiles. The formation of a corium pool and debris bed can result in significant temperature differences and high heat flux against the walls of the reactor vessel, causing a decrease in the integrity of the reactor vessel and reactor failure.Keywords: Corium, Uranium Dioxide (UO2), Zirconium Dioxide (ZrO2), Fluid Relocation, Moving Particle Semi-Implicit (MPS).

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“…In general, the results of this study indicate that the MPS method has the capacity to analyze the penetration behavior of melt in the instrument tube of the reactor vessel [5].…”

Section: Theoretical Backgroundmentioning

confidence: 72%

Section: Parameter III Survey: Lower Plenum Variation 4000k and Coriummentioning

confidence: 99%

Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

Irfan¹,

Humolungo²,

Mustari³

et al. 2023

CERiMRE

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Study on the safety characteristics of molten corium in-vessel retention of annular fuel core

Zhang

Wang

et al. 2023

Annals of Nuclear Energy

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Study on the Calculation Method of Molten Pool Decay Heat Distribution under IVR Condition

et al. 2021

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As an important strategy to mitigate severe accidents, the in-vessel retention (IVR) technique has been applied to the new generation of pressurized water reactor (PWR). However, under IVR conditions, the decay heat distribution in the molten pool is very uncertain because of the complexity of the molten pool and the calculation method limitations. To explore the calculation method and distribution of the decay heat of lower head molten pool under IVR conditions, the decay heat calculation method is developed based on Reactor Monte Carlo Code (RMC). The verification results show that the relative error of calculation result is generally within ± 0.25%. In addition, geometric modeling for lower head molten pools has been carried out, and distribution of the decay heat in two-layer and three-layer structures has also been accurately calculated. The calculation results indicate that the decay heat power spatial distribution is relatively uniform in the two-layer molten pool structure. The decay heat power at the center of the lower head decreases from 0.71°W/cm3 to 0.023°W/cm3 within 1d-5d. In the three-layer molten pool structure, the spatial distribution of the decay heat power is severely uneven due to the precipitation of heavy metal uranium. Besides, in actual engineering calculations, it should lay emphasis on the heat transfer characteristics and design margin of the upper part of the heavy metal layer and the lower part of the oxide layer because the maximum decay heat power appears at these two positions.

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Analysis of the configurations and heat transfer of corium pool in RPV lower plenum

Cited by 3 publications

References 11 publications

Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

Study on the safety characteristics of molten corium in-vessel retention of annular fuel core

Study on the Calculation Method of Molten Pool Decay Heat Distribution under IVR Condition

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