MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant

Jinrong, Qiu; Li, Longze; Tai, Yu‐Chong; Yao, Shiwei; Su, G.H.; Qiu, Suizheng

doi:10.1016/j.pnucene.2020.103509

Cited by 9 publications

(2 citation statements)

References 6 publications

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“…The results indicated that material migration after a severe accident was related to temperature. Jinrong 9 used MELCOR to study three accident mitigation measures after a LOCA in a floating nuclear power plant. The integrity of the entire reactor was not compromised, preventing the release of fission products into other compartments.…”

Section: Introductionmentioning

confidence: 99%

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Zhao

Zou²,

et al. 2022

Intl J of Energy Research

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Summary A simulation calculation model in the case of a severe accident such as a loss of coolant accident (LOCA) was established and calculated by MELCOR code in a marine pressurized water reactor. The effects of severe accidents on the hydrogen source term, release of the radionuclide source term, and the accident process were investigated, and the radiation consequences were analyzed. LOCA sensitivity analysis was conducted with different break sizes; the release and diffusion of source terms were analyzed. The results indicated that the hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size directly affected the accident progression. However, when the break exceeded a certain size, it did not affect the LOCA process. The break size may not change to change the release amount and migration rule of radionuclides such as Xe and I, and the fission product CsI, as final containment is in dynamic equilibrium in LOCA conditions. The contents of fission products released into the containment vessel, major loop, cavity, and the environment are sensitive to the break size. However, no special correlation is observed between the amount released and the break size. Highlights The hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size may not change to change the release amount and migration rule of radionuclides such as Xe, I, and CsI, as final containment is in dynamic equilibrium in LOCA conditions. No particular correlation is observed between the amount of radionuclide released and the break size.

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Section: Introductionmentioning

confidence: 99%

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Zhao

Zou²,

et al. 2022

Intl J of Energy Research

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“…Furthermore, floating nuclear power plants suffer much more complicated environment uncertainty since they operate under ocean condition. us, the probability of severe accidents of floating nuclear power plant SMRs might be relatively higher than the onshore SMRs [5]. erefore, a severe nuclear accident involving radionuclide leakage in atmosphere would pose a serious threat to personnel on the platform, the environment, and civilians in the vicinity of the floating nuclear power plant.…”

Section: Introductionmentioning

confidence: 99%

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

Zou

Liu

Huang

2021

Science and Technology of Nuclear Installations

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Floating nuclear power plant is a kind of nuclear power plant on a barge moored specifically in an area of the sea. In order to study the factors influencing airborne radionuclide dispersion induced by the loss-of-coolant accident in floating nuclear power plant, the floating nuclear power plant platform was taken as the research object, and the dispersion of airborne radionuclide under combined conditions of platform positions, wind directions, and break directions (north, south, west, and east) was simulated by the CFD (computational fluid dynamics) method. The results show that northern and southern breaks have less dangerous island area than western and eastern ones but have more platform dangerous area than the western and eastern ones. The risk of the southern break is the greatest, and that of the western break is the least. Rotating the floating nuclear power plant platform in a certain angle can reduce the damage of loss-of-coolant accident. The effects of the dose received by the personnel under the condition of the severe accident were evaluated based on previous research, showing that the inhalation effective dose and the effective dose of plume immersion exposure were less than the radiation dose limit of 0.25 Sv within two hours in the accident. The results of the study can provide reference for the design of floating nuclear power plant platform and the formulation of emergency plan.

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The economic and environmental assessment of alternative marine fuels and nuclear energy utilization on a floating power plant

Yuksel,

Konur,

Pamık

et al. 2024

Environ Sci Pollut Res

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MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant

Cited by 9 publications

References 6 publications

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

The economic and environmental assessment of alternative marine fuels and nuclear energy utilization on a floating power plant

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